Letter Sequence Supplement |
---|
|
|
MONTHYEARRS-09-104, Request for License Amendment to Revise Technical Specification 3.4.5, RCS Leakage Detection Instrumentation, to Allow Alternate Method of Verifying Drywell Leakage2009-08-28028 August 2009 Request for License Amendment to Revise Technical Specification 3.4.5, RCS Leakage Detection Instrumentation, to Allow Alternate Method of Verifying Drywell Leakage Project stage: Request ML1001200142010-01-15015 January 2010 Request for Additional Information Related to Alternate Method of Verifying Drywell Leakage Project stage: RAI RS-10-025, Supplemental Information Concerning Request for License Amendments to Revise Technical Specifications 3.4.5, RCS Leakage Detection Instrumentation.2010-02-0505 February 2010 Supplemental Information Concerning Request for License Amendments to Revise Technical Specifications 3.4.5, RCS Leakage Detection Instrumentation. Project stage: Supplement RS-10-096, Supplemental Information Concerning Request for License Amendment to Revise Technical Specification 3.4.5, RCS Leakage Detection Instrumentation2010-06-0202 June 2010 Supplemental Information Concerning Request for License Amendment to Revise Technical Specification 3.4.5, RCS Leakage Detection Instrumentation Project stage: Supplement ML1018806162010-08-16016 August 2010 Issuance of Amendments Authorizing Alternative Methods of Verifying Leakage within the Drywell Project stage: Approval 2010-02-05
[Table View] |
|
---|
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-23-104, 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-23-113, 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-23-097, 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-23-080, 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-23-077, 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-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-23-049, 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-23-007, 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-23-005, 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-22-119, 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-22-109, 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-22-102, 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-22-093, 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-22-095, 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 RS-22-096, Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval2022-08-10010 August 2022 Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval RS-22-098, Response to Request for Additional Information for Quad Cities Relief Request RV-11, Code Case OMN-282022-08-0101 August 2022 Response to Request for Additional Information for Quad Cities Relief Request RV-11, Code Case OMN-28 RS-22-094, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-09 to Permit Continued Application of Certain ASME Section XI 2013 Edition Non-Destructive Examination Requirements2022-07-25025 July 2022 Submittal of Sixth Inservice Inspection Interval Relief Request I6R-09 to Permit Continued Application of Certain ASME Section XI 2013 Edition Non-Destructive Examination Requirements RS-22-090, Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies2022-07-13013 July 2022 Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies RS-22-077, Response to Request for Additional Information for Quad Cities Relief Requests RV-08, Safety Relief Valves2022-06-30030 June 2022 Response to Request for Additional Information for Quad Cities Relief Requests RV-08, Safety Relief Valves RS-22-078, Response to Request for Additional Information for Quad Cities Relief Request RV-09, MSSVs2022-06-30030 June 2022 Response to Request for Additional Information for Quad Cities Relief Request RV-09, MSSVs RS-22-080, Withdrawal and Proposed Alternative I6R-08 Associated with Code Case N-921 for Sixth Inservice Inspection Intervals2022-06-0909 June 2022 Withdrawal and Proposed Alternative I6R-08 Associated with Code Case N-921 for Sixth Inservice Inspection Intervals RS-22-069, Constellation Nuclear Radiological Emergency Plan Addendum Revision. Includes EP-AA-1006, Addendum 3, Revision 10, Emergency Action Levels for Quad Cities Station2022-05-25025 May 2022 Constellation Nuclear Radiological Emergency Plan Addendum Revision. Includes EP-AA-1006, Addendum 3, Revision 10, Emergency Action Levels for Quad Cities Station RS-22-059, CFR50.46 Annual Report2022-05-0404 May 2022 CFR50.46 Annual Report RS-22-056, Constellation Radiological Emergency Plan Addendum Revision2022-04-21021 April 2022 Constellation Radiological Emergency Plan Addendum Revision RS-22-054, Withdrawal of Relief Request RV-10 Associated with the Sixth Inservice Testing Interval2022-04-13013 April 2022 Withdrawal of Relief Request RV-10 Associated with the Sixth Inservice Testing Interval 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-22-040, Response to Request for Additional Information Related to the License Amendment Request to Transition to GNF3 Fuel2022-04-11011 April 2022 Response to Request for Additional Information Related to the License Amendment Request to Transition to GNF3 Fuel 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-22-030, Submittal of Relief Request Associated with the Sixth Inservice Inspection Interval2022-03-25025 March 2022 Submittal of Relief Request Associated with the Sixth Inservice Inspection Interval 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 2024-01-03
[Table view] |
Text
Exelon Ceneratron Company, LLC www exeloncorp.com 4300 W~nfieldRoad Nuclear Warrenville, IL 60555 10 CFR 50.90 RS-10-096 June 2,2010 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 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:
Supplemental Information Concerning Request for License Amendment to Revise Technical Specification 3.4.5, "RCS Leakage Detection Instrumentation"
References:
- 1) Letter from J. L. Hansen (Exelon Generation Company, LLC) to U. S.
NRC, "Request for License Amendment to Revise Technical Specification 3.4.5, 'RCS Leakage Detection Instrumentation,' to Allow Alternate Method of Verifying Drywell Leakage," dated August 28, 2009 In Reference 1, Exelon Generation Company, LLC (EGC) submitted a request to amend Appendix A, "Technical Specifications," (TS) of Renewed Facility Operating License Nos.
DPR-19, DPR-25, DPR-29, and DPR-30 for Dresden Nuclear Power Station (DNPS), Units 2 and 3, and Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2, respectively. The proposed amendment revises TS 3.4.5, "RCS Leakage Detection Instrumentation," to support implementation of an alternate method of verifying that leakage in the drywell is within limits.
During a subsequent teleconference between the NRC (C. Gratton) and EGC (J. Schrage), the NRC requested supplemental information concerning the design of the QCNPS DWEDS and DWFDS, including the instrumentation and alarm systems. The attachment to this letter provides the supplemental information requested by the NRC.
June 2,2010 U. S. Nuclear Regulatory Commission Page 2 There are no regulatory commitments in this letter or the attachment.
Should you have any questions or require additional information, please contact Mr. John L.
Schrage at (630) 657-2821.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 2ndday of June 2010.
~ a n a g e -r Licensing
Attachment:
Supplemental Information - Quad Cities Nuclear Power Station, License Amendment Request to Revise Technical Specification 3.4.5, "RCS Leakage Detection Instrumentation"
ATTACHMENT Supplemental lnformation - Quad Cities Nuclear Power Station License Amendment Request to Revise Technical Specification 3.4.5, "RCS Leakage Detection Instrumentation" Additional Information By letter dated August 28,2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092400548), Exelon Generation Company, LLC (EGC) proposed to amend Appendix A, Technical Specifications (TS) of Renewed Facility Operating License Nos, DPR-19 and DPR-25 for Dresden Nuclear Power Station, Units 2 and 3 (DNPS), and Renewed Facility Operating License Nos. DPR-29 and DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2.
The August 28,2009 license amendment request (LAR) supported the implementation of an alternate method to quantify Reactor Coolant System (RCS) leakage in the primary containment (i.e., the drywell). The proposed alternate method uses the installed drywell equipment drain sump (DWEDS) monitoring system, with the drywell floor drain sump (DWFDS) overflowing to the DWEDS, to verify that RCS leakage in the drywell is within TS 3.4.4, "RCS Operational Leakage," limits. This configuration would only be used when the DWFDS monitoring system is unavailable.
In Attachment 1 to the August 28, 2009 LAR, EGC described the configuration and monitoring system for the DNPS and QCNPS DWFDS and DWEDS:
"The DWEDS monitoring system is similar to the DWFDS monitoring system. Leakage into the DWEDS is considered identified leakage. Identified leakage is composed of the normal seal and valve-packing leakage and does not represent a safety consideration as long as the leakage is small compared to the available reactor coolant makeup capacity.
The DWEDS monitoring system can be used in combination with the DWFDS monitoring system and other leak detection equipment to determine the source of leakage in the drywell. When a high level is reached in either the DWFDS or DWEDS, a level switch actuates to start the pumps when the pump discharge valves are open."
By letter dated August 6,2008 (ADAMS Accession No. ML082320087), EGC submitted an emergency LAR that requested a similar change to DNPS TS 3.4.5 that enabled EGC to implement, on a temporary basis, the alternate RCS leakage detection method for DNPS Unit 3.
In this emergency LAR, EGC described the configuration and monitoring system for the DNPS DWFDS and DWEDS:
"The drywell equipment drain sump is physically located next to the drywell floor drain sump, with the top of both sumps at the same elevation approximately three feet apart.
There are no obstructions between the two sumps to prevent or divert drywell floor drain sump overflow from reaching the drywell equipment drain sump. The control circuits for the two monitoring systems perform the same functions, and sump instrumentation consists of the same components and performs a similar function. Instruments for both monitoring systems are calibrated using the same plant procedure to satisfy TS SRs for functional testing and calibration. Recent performance of the drywell equipment drain sump pump flow instrumentation and sump level controls has demonstrated reliable performance."
Page 1 of 2
AlTACHMENT Supplemental Information - Quad Cities Nuclear Power Station License Amendment Request to Revise Technical Specification 3.4.5, "RCS Leakage Detection Instrumentation" During a subsequent teleconference between the NRC (C. Gratton) and EGC (J. Schrage) concerning the August 28, 2009 LAR, the NRC requested supplemental information concerning the design of the QCNPS DWEDS and DWFDS, including the instrumentation and alarm systems, similar to the information that had been previously provided for DNPS Unit 3.
EGC has verified that for both Unit 1 and Unit 2 at QCNPS, the DWEDS is physically located next to the DWFDS, with the top of both sumps at the same elevation, approximately three feet apart. There are no obstructions between the two sumps to prevent or divert drywell floor drain sump overflow from reaching the drywell equipment drain sump. The control circuits for the two monitoring systems perform the same functions, and sump instrumentation consists of the same components and performs a similar function. Instruments for both monitoring systems are calibrated using the same plant procedure to satisfy TS SRs for functional testing and calibration. Thus, the design of the QCNPS DWFDS and DWEDS, including the associated instrumentation and alarm systems, will ensure that there would be no significant extension of operator response time when one sump is overflowing into the other sump.
Page 2 of 2