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MONTHYEARML0701804442007-01-29029 January 2007 Withholding from Public Disclosure, Polestar-prepared Calculation, H21C092, U1 LOCA W/Loop, AST Methodology Project stage: Other ML0714100472007-05-21021 May 2007 Request for Additional Information Regarding Nine Mile Point Nuclear Station, Unit No. 1, Implementation of Alternative Source Term Project stage: RAI ML0715700092007-06-0808 June 2007 Meteorology Request for Additional Information Regarding Nine Mile Point Nuclear Station, Unit No. 1, Implementation of Alterative Source Term Project stage: RAI ML0722201462007-08-0101 August 2007 License Amendment Request Pursuant to 10 CFR 50.90: Application of Alternative Source Term - Response to NRC Request for Additional Information Project stage: Response to RAI ML0726203612007-09-19019 September 2007 License Amendment Request Pursuant to 10 CFR 50.90: Application of Alternative Source Term - Supplemental Information Project stage: Supplement 2007-06-08
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Category:Letter
MONTHYEARML24249A1362024-09-0404 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 NMP1L3582, Annual Radioactive Environmental Operating Report2024-05-15015 May 2024 Annual Radioactive Environmental Operating Report 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 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 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 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 ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 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 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) 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 IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 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)) 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 ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 2024-09-04
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Keith J. Poison P.O. Box 63 Vice President-Nine Mile Point Lycoming, New York 13093 315.349.5200 315.349.1321 Fax 0 Constellation Energy Nine Mile Point Nuclear Station August 1, 2007 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION:
Document Control Desk
SUBJECT:
Nine Mile Point Nuclear Station Unit No. 1; Docket No. 50-220 License Amendment Request Pursuant to 10 CFR 50.90: Application of Alternative Source Term -Response to NRC Request for Additional Information (TAC No.MD3896)
REFERENCES:
(a) Letter from T. J. O'Connor (NMPNS) to Document Control Desk (NRC), dated December 14, 2006, License Amendment Request Pursuant to 10 CFR 50.90: Application of Alternative Source Term (b) Letter from M. J. David (NRC) to T. J. O'Connor (NMPNS), dated June 8, 2007, Meteorology Request for Additional Information Regarding Nine Mile Point Nuclear Station, Unit No. 1, Implementation of Alternative Source Term (TAC No. MD3896)(c) Letter from K. J. Poison (NMPNS) to Document Control Desk (NRC), dated July 17, 2007, License Amendment Request Pursuant to 10 CFR 50.90: Application of Alternative Source Term -Response to NRC Requests for Additional Information (TAC No. MD3896)Nine Mile Point Nuclear Station, LLC (NMPNS) hereby transmits supplemental information requested by the NRC in support of a previously submitted application for amendment to Nine Mile Point Unit 1 (NMPI) Renewed Operating License DPR-63. The initial application, dated December 14, 2006 (Reference a) proposed to revise the accident source term used in the design basis radiological consequence analyses in accordance with 10 CFR 50.67. The proposed accident source term revision would replace the current methodology that is based on Technical Information Document (TID)-14844 with the alternative source term methodology described in Regulatory Guide 1. 183.By letter dated June 8, 2007 (Reference b), the NRC requested additional information regarding the subject license amendment request. NMPNS provided responses to the request for additional information
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Document Control Desk August 1, 2007 Page 3 Attachments:
(1)Nine Mile Point Unit I -Response to NRC Request for Additional Information Regarding Proposed Revision to the Accident Source Term cc: S. J. Collins, NRC M. J. David, NRC Resident Inspector, NRC J. P. Spath, NYSERDA ATTACHMENT (1)NINE MILE POINT UNIT 1 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED REVISION TO THE ACCIDENT SOURCE TERM Nine Mile Point Nuclear Station, LLC August 1, 2007 ATTACHMENT (1)NINE MILE POINT UNIT 1 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED REVISION TO THE ACCIDENT SOURCE TERM By letter dated December 14, 2006, Nine Mile Point Nuclear Station, LLC (NMPNS) submitted a license amendment request to implement the alternative source term methodology for Nine Mile Point Unit 1 (NMP1). The NRC requested additional information regarding this license amendment request in a letter dated June 8, 2007. NMPNS provided responses to the request for additional information by letter dated July 17, 2007, with the exception of Request AADB-8. This attachment provides the response to Request AADB-8. The NRC request is repeated (in italics), followedby the NMPNS response.Request AADB-8 The NRC staff notes that 60.7 meter wind measurements, rather than the 9.4 meter measurements, were used in the calculation of the ground level EAB and LPZ x/Q values. In addition, the 60.7 meter wind measurements and atmospheric stability measurements between the 60.7 and 9.4 meter levels were used, to calculate the elevated release X/Q values for releases from the 106. 7 meter NMP1 stack NRC Regulatory Issue Summary 2006-04, *"Experience With Implementation of Alternative Source Terms, " dated March 7, 2006, states that when running the offsite atmospheric dispersion model PA VAN, two or more files of meteorological data representative of each potential release height should be used if X/Q values are being calculated for pathways with significantly different release heights. Please provide justification that use of the 60.7 meter data is adequate for generation of both the ground level and elevated release X/Q values used in the dose assessment.
Response PAVAN includes a methodology for addressing differences in release height and measurement height.The height above plant grade of the release point (HS) and the height above ground level at which the wind speed was measured (TOWERH) are model inputs. PAVAN accounts for differences in release and wind measurement height if HS in not equal to TOWERH (ADJWND subroutine) using the following relationship:
UR =UM(HR/TH)p (1)where: UR = wind speed adjusted to the height of release (meter/sec), UM = wind speed at the level of measurement (meter/sec), HR = height of release (meter), TH = height at which wind speed UM was measured (meter), and P = 0.25 for unstable and neutral atmospheric conditions and 0.50 for stable conditions.
For ground-level releases, when HR = 10 meter and TH = 60.7 meter, the adjusted wind speed is UR =0.6 37UM (unstable/neutral) and UR = 0.406UM (stable).
Thus, the 60.7 meter wind measurement data is properly reduced to simulate winds at the lower release height of 10 meter. These factors were applied to the X/Q values calculated in calculation H21C076 and reported in Attachment (7) of the December 14, 2006, NMPNS submittal.
A survey of the 9.4 meter and 60.7 meter wind measurement data shows differences in wind speed and direction.
At the 60.7 meter level the wind speeds are typically 1 to 3 meter/sec faster. Also, a difference I of 2 ATTACHMENT (1)NINE MILE POINT UNIT 1 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED REVISION TO THE ACCIDENT SOURCE TERM in the directional component occurs for lower wind speeds (< 4 meter/sec).
At the 9.4 meter level most of the lower speed wind is from the land sectors (approximately 2:1 compared to the lake sectors).
There is little directional variation in the lower speed wind at the 60.7 meter level. Conversely, for moderate wind speeds (> 4 meter/sec), more wind is from the lake sectors at the 9.4 meter level.To assess the -impact on the PAVAN models, sensitivity calculations were performed using the 9.4 meter wind measurement data to determine ground level release X/Q values. Comparison of these values to the X/Q values used in performing the evaluations to support the December 14, 2006 submittal determined that the calculated X/Q values based on the 60.7 meter data were conservative (i.e., higher) relative to the values based on the 9.4 meter data, both for the exclusion area boundary (0 to 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) and for the low population zone (LPZ) for the 0 to 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time periods; however, the calculated LPZ X/Q values for the 1-4 day and 4-30 day time periods were non-conservative.
To ascertain the impact of the non-conservative LPZ X/Q values for the 1-4 day and 4-30 day periods, sensitivity calculations were performed using the RADTRAD loss of coolant accident (LOCA) models.The dose at the LPZ was recalculated for the three ground level release pathways.
The resultant LPZ TEDE doses were found to be bounded by those reported in the December 14, 2006 submittal.
Therefore, the use of 60.7 meter wind measurement data for the determination of ground level release X/Q values results in bounding offsite doses and is therefore conservative.
The onsite meteorological measurement program is described in the Nine Mile Point Unit 2 (NMP2)Updated Safety Analysis Report, Section 2.3.3, and was accepted by the NRC in their Safety Evaluation Report for NMP2 (NUREG-1047).
For both the preoperational and operational measurements programs, the meteorological tower height of 200 feet was and is not suitable for collecting wind measurement data at higher elevations, such as the 350-foot tall main stack. The current stack release X/Q values were calculated with PAVAN using the 60.7 meter level wind measurement data. As described above, the PAVAN model properly accounts for the difference in release and measurement height by increasing the wind speeds using Equation (1) above.2 of 2