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TAC:MD7539, DC Electrical Rewrite - Update to TSTF-360, DC Electrical Rewrite (Withdrawn, Closed) TAC:MD7540, DC Electrical Rewrite - Update to TSTF-360, DC Electrical Rewrite (Withdrawn, Closed) |
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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-23-104, 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
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Exe I ~, n~M m 1 Nuclear Exelon Generation www.exeloncorpcom 4300 Winfield Road Warrenville, IL 6055 ,
RS-08-102 August 14, 2008 U . S . Nuclear Regulatory Commission ATTN : Document Control Desk Washington, DC 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:
Additional Information Supporting Request for License Amendment to Establish Total Battery Connector Resistance Acceptance Criteria in Technical Specifications Surveillance Requirements 3 .8.4.2 and 3.8.4.5
References:
- 1. Letter from J . L. Hansen (Exelon Generation Company, LLC) to U . S.
NRC, "Request for License Amendment to Establish Total Battery Connector Resistance Acceptance Criteria in Technical Specifications Surveillance Requirements 3.8 .4.2 and 3.8.4.5," dated December 21, 2007
- 2. Letter from J . S . Wiebe (U. S. NRC) to C . G. Pardee (Exelon Generation Company, LLC), "Quad Cities Nuclear Power Station, Units 1 and 2 -
Request for Additional Information Related to License Amendment to Establish Total Battery Connector Resistance Acceptance Criteria in Technical Specifications (TAC Nos. MD7539 and MD7540)," dated July 18, 2008 In Reference 1, Exelon Generation Company, LLC (EGC) requested an amendment to Renewed Facility Operating License Nos . DPR-29 and DPR-30 for Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2. The proposed change revises Technical Specification (TS)
Surveillance Requirements (SR) 3.8.4.2 and 3.8.4 .5 to add an additional acceptance criterion to verify that the total battery connector resistance is within the pre-established limits that ensure the QCNPS safety-related batteries can perform their intended design function .
In Reference 2, the NRC requested additional information to complete its review . In response to Reference 2, EGC is providing the attached information.
August 14, 2008 U . S. Nuclear Regulatory Commission Page 2 EGC has reviewed the information supporting a finding of no significant hazards consideration that was previously provided to the NRC in Attachment 1 of Reference 1 . The information provided in this submittal does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration.
There are no regulatory commitments contained in this letter . Should you have any questions concerning this letter, please contact Michelle Yun at (630) 657-2818 .
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 14th day of August 2008 .
cc: NRC Senior Resident Inspector NRC Regional Administrator, Region III Attachment : Response to Request for Additional Information
ATTACHMENT NRC_ Request 1 In the November 28, 2006, Component Design Bases Inspection report referenced in your license amendment request, the NRC inspectors identified that the 125 volt direct current safety-related batteries would be incapable of meeting their design basis function if the inter-cell connection resistance were allowed to increase to the existing TS allowed value (i.e., 150 micro-ohms) . Describe the basis for maintaining the existing150 [sic] micro-ohm inter-cell connection resistance value in TS SR 3.8.4.2 and 3.8 .4.5.
Response
Technical Specification (TS) Surveillance Requirements (SR) 3.8 .4.2 and 3.8.4.5 establish the requirement to perform inspections and measurements to detect localized battery connector degradation . A measurement of inter-cell and terminal connection resistance provides an indication of localized deterioration that could unacceptably degrade local battery performance if left uncorrected. The specific resistance value (150 micro-ohms) was not initially established as an absolute limit for battery operability. The value was based on industry experience as a threshold for identifying localized degradation so that issues potentially affecting battery performance are promptly identified and corrected. EGC concludes that SR 3.8.4.2 and 3 .8.4.5 will continue to serve this function while the proposed expanded SR provide the necessary surveillance of total battery resistance to ensure battery operability.
NRC Request 2 In the license amendment request, the license [sic] stated that in response to the nonconservative [sic] TS value (i .e., 150 micro-ohms) it has initiated a compensatory measure to ensure safety-related battery operability by declaring the 125 and 250 volt direct current batteries inoperable if any inter-cell resistance exceeds 70 micro-ohms . Describe the methodology and calculation used to determine the inter-cell resistance value of 70 micro-ohms .
Does this value represent the worst-case inter-cell resistance (i.e., the operability limit)?
Response
The 70 micro-ohm limit is based on two factors associated with the 125 VDC batteries. The first factor is the inherent voltage drop that exists between each inter-cell connector when the battery is new. This voltage drop is typically 20 millivolts and is accounted for in the battery manufacturer's discharge curves . Using Ohm's Law and rated current (750 amps), an inherent inter-cell resistance value can be determined . In this case, this value is 26.67 micro-ohms . In other words, when the battery voltage drops to its 105 VDC UFSAR minimum value, 26.67 micro-ohms will nominally be found across each inter-cell connector.
The second factor is the amount of voltage margin that exists when a battery service test is performed. During a service test, the battery is subjected to its worst case load profile. The voltage at the battery's terminals is monitored to verify that it does not drop below 105 VDC as required per the UFSAR. The lowest recorded voltage for the limiting battery was found to be 107.2 VDC . Therefore, 2.2 VDC of margin exists for this battery. Using Ohm's Law, this 2.2 VDC of margin can be converted to a resistance when the battery's maximum current draw is considered . This resistance, when divided by the number of inter-cell connectors, produces a value of 44 micro-ohms . When the 44 micro-ohm value is added to the inherent value of 26.67 (conservatively rounded to 26) micro-ohms, a 70 micro-ohm limit is established. Note that a 120% design factor is included in the 44 micro-ohm value to account for future load growth .
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ATTACHMENT The inputs to this calculation are periodically verified and after load additions to the battery to ensure the 70 micro-ohm limit remains valid . The 70 micro-ohm limit is conservatively applied to the 250 VDC batteries because the 125 VDC batteries are the most limiting case .
The 70 micro-ohm limit was determined by conservatively assuming all inter-cell and terminal connections are degraded to the same degree at the same time . This worst-case scenario is unlikely and the compensatory measure was deemed an appropriate and conservative response to the NRC violation referenced below and was established as a short-term action in accordance with NRC Administrative Letter 98-10, "Dispositioning of Technical Specifications That Are Insufficient to Assure Plant Safety ." It is not feasible to establish a localized terminal/connector resistance limit for battery operability because localized degradation does not necessarily reflect overall battery performance. As noted in the response to NRC Request 1, the proposed expanded SRs provide the necessary surveillance of total battery resistance to ensure battery operability is maintained .
NRC Request 3 Describe the controls that will be implemented to direct the QCNPS staff how and when (i .e.,
how frequently?) to update the Individual Battery Total Connector Resistance Acceptance Criteria that you proposed locating in the TS bases .
Response
Battery total connector resistance acceptance criteria will be maintained in a formal calculation.
This calculation receives its inputs from the 125 VDC and 250 VDC battery sizing calculations which are revised when the loading on the batteries is changed (e.g., modifications) . There is a formal administrative tie between the inter-cell connection calculation and the battery sizing calculation such that they will both be revised when battery loading changes .
The inter-cell resistance calculation contains both a total allowable resistance limit and the TS bases acceptance criteria. The TS bases acceptance criteria will always be less than the total allowable resistance limit to allow for minor load changes to be added to the battery without revising the TS bases. Changes to the TS bases are governed by TS 5.5.10, "Technical Specifications (TS) Bases Control Program."
Calculations are controlled by EGC procedure CC-AA-309, "Control of Design Analyses," which contains administrative requirements for calculation revisions. In this case, if battery loading changes, the battery sizing calculations as well as all related calculations will also be revised at that time . Since the inter-cell connection resistance calculation establishes the values in the TS bases, these TS bases values will be reviewed anytime a battery load addition or reduction occurs .
Reference:
Letter from A. M. Stone (U . S . NRC) to C. M. Crane (Exelon Generation Company, LLC),
"Quad Cities Nuclear Power Station, Units 1 and 2, NRC Component Design Bases Inspection (CDBI), Inspection Report 05000254/2006003(DRS), 05000265/2006003(DRS),"
dated November 28, 2006