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MONTHYEARML13197A2212013-07-0505 July 2013 License Amendment Request Pursuant to 10 CFR 50.90: Standby Liquid Control System - Increase in Isotopic Enrichment of Boron-10 Project stage: Request ML13225A1372013-08-13013 August 2013 MF2462, Acceptance of Requested Licensing Action License Amendment Request on Standby Liquid Control System - Increase in Isotopic Enrichment of Boron-10 Project stage: Acceptance Review ML13316B1072013-11-0101 November 2013 License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus Project stage: Request ML13310A8172013-11-0606 November 2013 MF2462, Draft Rais, MF2462, LAR Standby Liquid Control System - Increase in Isotopic Enrichment of Boron-10 Project stage: Draft RAI ML13345A6092013-12-0606 December 2013 Response to Request for Additional Information Regarding License Amendment Request Pursuant to 10 CFR 50.90: Standby Liquid Control System - Increase in Isotopic Enrichment of Boron-10 Project stage: Response to RAI ML14036A0052014-03-14014 March 2014 Issuance of Amendment License Amendment Request Pursuant to 10 CFR 50.90: Standby Liquid Control System - Increase in Isotopic Enrichment of Boron-10 Project stage: Approval ML14169A0342014-06-13013 June 2014 License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus - Revision 1 Project stage: Request 2013-07-05
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Category:Letter
MONTHYEARML24268A3382024-10-16016 October 2024 Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2890, Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)2024-10-0404 October 2024 Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6) ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing IR 05000220/20243022024-10-0303 October 2024 Initial Operator Licensing Examination Report 05000220/2024302 ML24190A0012024-09-26026 September 2024 Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024 Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000220/20240052024-08-29029 August 2024 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005) IR 05000220/20240102024-08-22022 August 2024 Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024 Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000220/20240022024-08-0505 August 2024 Integrated Inspection Report 05000220/2024002 and 05000410/2024002 ML24215A3002024-08-0202 August 2024 Operator Licensing Examination Approval NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024 Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML24213A1412024-07-31031 July 2024 Requalification Program Inspection NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations ML24198A0852024-07-16016 July 2024 Senior Reactor and Reactor Operator Initial License Examinations RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000220/20244012024-05-30030 May 2024 Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only) ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable ML24158A2052024-05-15015 May 2024 Annual Radioactive Environmental Operating Report NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2 IR 05000220/20240012024-05-10010 May 2024 Integrated Inspection Report 05000220/2024001 and 05000410/2024001 RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds 05000410/LER-2024-001, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024 Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024 2023 Annual Environmental Operating Report NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024 Core Operating Limits Report ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 ML24074A2812024-03-14014 March 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable IR 05000220/20230062024-02-28028 February 2024 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006) IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024 Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 05000220/LER-2023-002, Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 122023-12-15015 December 2023 Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 12 NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station 2024-09-04
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Christopher R. Costanzo Office: 315.349.5200 Vice President - Nine Mile Point Fax: 315.349.1321 E-mail: Christopher.Costanzo@cengllc.com CENG.
a joint venture of 0Energy nst"eaIýi 66-'eDF NINE MILE POINT NUCLEAR STATION December 6, 2013 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk
SUBJECT:
Nine Mile Point Nuclear Station Unit No. 2" Docket No. 50-410 Response to Request for Additional Information Regarding License Amendment Request Pursuant to 10 CFR 50.90: Standby Liquid Control System - Increase in Isotopic Enrichment of Boron- 10
REFERENCES:
(a) Letter from P. M. Swift (NMPNS) to Document Control Desk (USNRC), License Amendment Request Pursuant to 10 CFR 50.90: Standby Liquid Control System
- Increase in Isotopic Enrichment of Boron- 10, dated July 5, 2013 (ML13197A221)
On July 5, 2013 (Reference a), Nine Mile Point Nuclear Station, LLC (NMPNS) submitted a request for an amendment to Nine Mile Point Unit 2 (NMP2) Renewed Operating License (OL) NPF-69 to increase the isotopic enrichment of boron-10 in the sodium pentaborate solution used to prepare the neutron absorber solution in the Standby Liquid Control System (SLS). On November 6, 2013, the U.S. Nuclear Regulatory Commission (NRC) issued a Request for Additional Information (RAI) via email regarding the NMP2 license amendment request. A subsequent teleconference with the NRC reviewer and staff on November 14, 2013 provided clarification of the questions and the agreed to scope of response. provides the NMPNS response to the 4 questions in the NRC RAI.
This supplemental information does not affect the No Significant Hazards Determination analysis provided by NMPNS in Reference (a). Pursuant to 10 CFR 50.91(b)(1), NMPNS has provided a copy of this supplemental information to the appropriate state representative. This letter contains no new regulatory commitments.
Document Control Desk December 6, 2013 Page 2 Should you have any questions regarding the information in this submittal, please contact Everett (Chip).
Perkins, Director - Licensing, at (315) 349-5219.
I declare under penalty of perjury that the foregoing is true and correct. Executed on December 6, 2013.
Very truly yours, CRC/KJK/STD
Attachment:
Response to Request for Additional Information cc: Regional Administrator, Region I, NRC Resident Inspector, NRC Project Manager, NRC A. L. Peterson NYSERDA
ATTACHMENT RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Nine Mile Point Nuclear Station, LLC December 6, 2013
ATTACHMENT RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Each individual NRC question is repeated (in italics), followed by the NMPNS response.
NRC RAI #1 The application describes the changes to the volumes, concentrations and enrichments but does not describe physical plant changes to the SLC [Standby Liquid Control] System. Is the system being physically changed? Describe the svstem (storage tank size, pumps location and its actuationmechanism during A TWS), provide a schematic of the systems, and describe the functionality of the proposed SLC System for NMP2 [Nine Mile Point Unit 2] including the operator actions necessary during an A TWS
[Anticipated Transient Without Scram].
NMPNS Response The proposed license amendment only affects the isotopic enrichment of boron-10 in the sodium pentaborate solution used to prepare the neutron absorber solution in the SLC. The proposed license amendment request does not require any physical modifications to the SLC system including its function and operation. As discussed in a teleconference with the NRC on November 14, 2013, the NRC staff noted that it is acceptable to refer to specific sections of the NMP2 Updated Safety Analysis Report (USAR), rather than include a description and schematic of the system. The SLC System is described in Section 9.3.5, Standby Liquid Control System, of the NMP2 USAR. The SLC System Piping and Instrument Diagram is shown in NMP2 USAR Figure 9.3-17a, Standby Liquid Control.
The SLC system initiates upon receiving High Dome Pressure signal or Reactor Low Vessel Level 2 with Average Power Range Monitor (APRM) confirmation (power > 4%) with 98 seconds nominal time delay.
The SLC system initiation logic is shown in NMP2 USAR Figure 7.6-9, Redundant Reactivity Control System.
The only difference is that the negative reactivity insertion rate is about 4 times higher. Therefore, the injection time is shorter with the changes defined in the proposed license amendment request.
The SLC system initiates automatically during an ATWS event and manual operator actions are not required.
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ATTACHMENT RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION NRC RAI #2 Please provide a design rationalefor the assumptions regarding SLC System Petformances listed in Table I of the July 5. 2013 submittal. Specifically explain why the range of values was chosen for minimum boron-JO enrichmentfor A TWS analysis and SLC System pump flow rate to support.
- a. The application states the required minimum volumes for the 13.6 wt% [weight percent] and 14.4 wt% solution volumes were derived by determining the minimum solution volume and then increasingthe volume to accountfor: 1) the dead volume not pumped in the reactorthat remains in the SLC System and HPCS [High Pressure Core Spray] piping, and 2) instrument accuracy.
Please explain how these volumes were derived. Please include the methodologies and the basis for the criteria used.
NMPNS Response The 92% minimum boron- 0 enrichment is primarily based on injection of sufficient negative reactivity as soon as practical to offset the impact of a future modification, while maintaining the suppression pool heatup approximately same.
GEH issued a Safety Communication (SC) 10-13, Standby Liquid Control System Dilution Flow, alerting utilities that there is a potential that the solution injected into the vessel may be diluted due to a small flow through an orifice from the makeup water system. The maximum expected dilution flow is less than 1 gpm. Therefore, the suction flow from the SLC storage tank could be 81.4 gallons per minute (gpm)
(82.4 gpm total pump flow - I gpm dilution flow). NMP2 conservatively used an 80 gpm suction flow rate from the SLC storage tank.
The minimum tank volume requirements were calculated as follows:
- First, the solution volume necessary to bring reactor coolant boron concentration to 780 parts per million (ppm) of natural boron plus 25% margin is calculated. For a 13.6 wt% sodium pentaborate solution concentration, the required solution volume is 1,178 gallons. For 14.4 wt%
solution concentration, the required volume is 1,108 gallons.
- Following an injection, some of the solution will remain in the piping between the tank and the injection points (HPCS injection spargers) once the SLC pump trips on low level. This volume (239.4 gallons) is added to the above volume.
- The SLC pumps automatically trip when the sensed tank level is "zero", 10.23 inches above the tank bottom. The overall instrumentation loop uncertainty in the level measurement is 3.6 inches (same as prior to the proposed license amendment request), which equates to 143 gallons.
Conservatively, the SLC pumps are assumed to trip 3.6 inches above the "zero" level.
- The minimum required tank volume (above tank "zero" level) calculated above is further adjusted for solution temperature variation with added margin (approximately 40 gallons). The minimum required inventory above the tank "zero" level is 1,600 gallons. NMP2 administratively maintains the tank solution between 1,800 and 2,000 gallons above the tank "zero" level.
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ATTACHMENT RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION NRC RAI #3 With respect to maintainingsuppressionpool pH >7.0, please provide the methodologies used to generate the minimum sodium pentaborate solution volume requiredfor injection post-LOCA [Loss of Coolant Accident]for adequatepH control at the limiting concentrationas given in the submittal as 1, 065 gallon for a sodium pentaborate concentration of 13.6%. Also provide an explanation regarding how the mnaximum time available to add boron is determined.
NMPNS Response The suppression pool pH calculation utilizes the methodology described in NUREG/CR-5950, Iodine Evolution and pH Control. This methodology was used earlier by NMP2 in support of Alternate Source Term License Amendment Request approved by the NRC on May 29, 2008 (ML081230439, ML081560633).
The maximum time available to add boron is based on a SLC storage tank operating heater failure scenario. The operating heater is assumed to fail in the ON position (heater continues to heat the liquid) and no operator action is taken following the LOCA event to turn-off the heater. Under this conservative scenario, the solution temperature increases. At approximately 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> into the LOCA event, the solution temperature would be at the point such that the Net Positive Suction Head - Available (NPSHA) is reduced to Net Positive Suction Head - Required (NPSHR). Therefore, in the heater failure scenario, the SLC pump may not function after 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />.
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ATTACHMENT RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION NRC RAI #4 With respect to Net Positive Suction Head Available (NPSH.,) for SLC System pumps, the proposed reduction in the minimum volume for SLC System storage tank results in a reduction in the static head available to provide NPSHA and the calculation that determines the SLC System pumnp NPSHA did not take any creditfor the static head above the SLC System storage tank zero level. Please describe any difference in the SLC System pump specifications between the current ones and the ones to be usedfor proposed change of the minimum SLC System storage tank andjustiy that the proposed NPSH4 for the SLC System pumps adequate.
NMPNS Response The proposed license amendment request does not require any modifications to the SLC pumps, piping, or tank. Therefore, there is no change to the SLC pump specification.
The SLC pump NPSH calculation uses tank "zero" level as its basis for calculating NPSHA, same as before the proposed change, which has been confirmed through the review of the calculation. In addition, the pump flow remains the same as before. Therefore, SLC pump NPSH margin is not affected by the license amendment request.
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