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MONTHYEARML0809305052008-03-20020 March 2008 License Amendment Request for Full Scope Implementation of the Alternative Source Term Project stage: Request ML0815603952008-05-28028 May 2008 License Amendment Request for Full Scope Implementation of the Alternative Source Term, Revisions to Control Room Atmospheric Dispersion Factors Project stage: Request ML0828300142008-10-0606 October 2008 Response to Request for Additional Information License Amendment Request for Implementation of Alternative Source Term Project stage: Response to RAI ML0835903422008-12-17017 December 2008 Response to Request for Additional Information Related to the License Amendment Request for Implementation of Alternative Source Term Project stage: Response to RAI ML0904106392009-02-10010 February 2009 Request for Additional Information (RAI) Regarding Proposed License Amendment Request for Implementation of Alternative Source Term Project stage: RAI ML0905406822009-02-12012 February 2009 Response to Request for Additional Information Related to the License Amendment Request (LAR) for Implementation of Alternative Source Term Project stage: Response to RAI ML0905402882009-02-23023 February 2009 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for Hearing Project stage: Other ML0908607762009-03-25025 March 2009 Response to Request for Additional Information Related to the License Amendment Request (LAR) for Implementation of Alternative Source Term (AST) Project stage: Response to RAI ML0908906272009-03-31031 March 2009 Issuance of Amendments Regarding Adoption of the Alternative Source Term Radiological Analysis Methodology Project stage: Approval 2009-02-10
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Category:Letter
MONTHYEARIR 05000369/20240032024-11-0404 November 2024 Integrated Inspection Report 05000369/2024003 and 05000370/2024003 ML24303A4212024-10-30030 October 2024 Mcguire Nuclear Station, Units 1 & 2, Notification of an NRC Fire Protection Team Inspection FPTI NRC 05000369/2025010, 05000370/2025010 and Request for Information RFI IR 05000369/20244022024-10-0808 October 2024 Security Baseline Inspection Report 05000369/2024402 05000370/2024402 IR 05000369/20240052024-08-26026 August 2024 Updated Inspection Plan for McGuire Nuclear Station, Units 1 and 2, (Report 05000369-2024005 and 05000370-2024005) IR 05000369/20244042024-08-0101 August 2024 Cover Letter Security Baseline Inspection Report 05000369/2024404 and 05000370/2024404 IR 05000369/20253012024-07-29029 July 2024 Notification of Licensed Operator Initial Examination 05000369/2025301 and 05000370/2025301 IR 05000369/20244032024-07-25025 July 2024 – Cyber Security Inspection Report 05000369/2024403 and 05000370/2024403 Rev IR 05000369/20240022024-07-24024 July 2024 Integrated Inspection Report 05000369/2024002 and 05000370/2024002 ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000369/20244012024-07-0303 July 2024 – Security Baseline Inspection Report 05000369/2024401 and 05000370/2024401 ML24176A2802024-06-26026 June 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000369-2024404 and 05000370-2024404) IR 05000369/20240112024-06-0404 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000369/2024011 and 05000370/2024011 ML24149A1772024-05-28028 May 2024 NRC Response to Duke Energy 2025 FOF Schedule Change Request (Catawba and McGuire) IR 05000369/20240012024-05-0808 May 2024 Integrated Inspection Report 05000369-2024001 and 05000370-2024001 and 07200038-2024001 ML24110A0382024-04-30030 April 2024 – Correction to Issuance of Amendment Nos. 330 and 309, Regarding Implementation of Technical Specifications Task Force (TSTF) Traveler TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf ML24100A8742024-04-10010 April 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000369/2024403; and 05000370/2024403 ML24052A3062024-04-0808 April 2024 Issuance of Amendment Nos. 331 & 310, Regarding Adoption of Title 10 of Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants ML24031A5402024-03-26026 March 2024 Issuance of Amendment Nos. 330 and 309 Regarding Implementation of TSTF 505,Rev. 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML24085A2402024-03-21021 March 2024 Requalification Program Inspection - McGuire Nuclear Station IR 05000369/20230062024-02-28028 February 2024 Annual Assessment Letter for McGuire Nuclear Station, Units 1 and 2 - NRC Inspection Report 05000369/2023006 and 05000370/2023006 ML24024A2182024-02-0505 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000369/20230042024-01-31031 January 2024 Integrated Inspection Report 05000369/2023004 and 05000370/2023004 ML24019A1392024-01-25025 January 2024 TSTF 505 and 50.69 Audit Summary ML24019A2002024-01-24024 January 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000369/20234022023-12-14014 December 2023 – Material Control and Accounting Program Inspection Report 05000369/2023402 and 05000370/2023402 05000369/LER-1923-001, Automatic Actuation of the 1A Motor Driven Auxiliary Feedwater Pump Due to Human Error2023-12-13013 December 2023 Automatic Actuation of the 1A Motor Driven Auxiliary Feedwater Pump Due to Human Error ML23317A2272023-11-17017 November 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Transmittal of Dam Inspection Report - Non-Proprietary ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000369/20230032023-10-24024 October 2023 Integrated Inspection Report 05000369/2023003 and 05000370/2023003; and Inspection Report 07200038/2023001 IR 05000369/20240102023-10-13013 October 2023 Notification of McGuire Nuclear Station Comprehensive Engineering Team Inspection – U.S. Nuclear Regulatory Commission Inspection Report 05000369, 370/2024010 IR 05000369/20230102023-10-13013 October 2023 Age Related Degradation Inspection Report 05000369/2023010 and 05000370/2023010 ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds IR 05000369/20233012023-09-20020 September 2023 William B. McGuire Nuclear Station - NRC Examination Report 05000369/2023301 and 05000370/2023301 ML23230A0652023-08-31031 August 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Relief Request Use of Later Edition of ASME Code ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000369/20230052023-08-25025 August 2023 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 (Report 05000369/2023005 and 05000370/2023005) IR 05000369/20234012023-08-0404 August 2023 – Security Baseline Inspection Report 05000369/2023401 and 05000370/2023401 (OUO-SRI) Cover IR 05000369/20230022023-07-28028 July 2023 Integrated Inspection Report 05000369/2023002 and 05000370/2023002 IR 05000369/20234202023-07-24024 July 2023 – Security Baseline Inspection Report 050003692023420 and 050003702023420 ML23206A0092023-07-24024 July 2023 William B. McGuire Nuclear Station – Operator Licensing Written Examination Approval 05000369/2023301 and 05000370/2023301 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23159A2712023-06-20020 June 2023 William B. McGuire Nuclear Station, Unit 1 - Relief Request Impractical Reactor System Welds ML23237A2672023-06-13013 June 2023 June 13, 2002 - Meeting Announcement - McGuire and Catawba Nuclear Stations 50-369, 50-370 and 50-413, 50-414 ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined ML23124A0862023-05-0303 May 2023 Cycle 29, Revision 1, Core Operating Limits Report (COLR) ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI IR 05000369/20230012023-05-0101 May 2023 Integrated Inspection Report 05000369/2023001 and 05000370/2023001 ML23115A2122023-05-0101 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23094A1832023-04-18018 April 2023 Audit Plan TSTF-505, Rev. 2, RITSTF Initiative 4B & 10 CFR 50.69, Risk-Informed Categorization & Treatment of Structures, Systems & Components for Nuclear Power Reactors (EPIDs L-2023-LLA-0021 & L-2023-LLA-0022) ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility 2024-08-26
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24197A1702024-07-15015 July 2024 Request for Additional Information Two Proposed Alternatives (RA-23-0242) for the Inspection of Reactor Vessel Closure Head Penetrations ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23142A2732023-05-22022 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML23030B9032023-01-30030 January 2023 Formal Release of RAIs for McGuire Unit 1, Relief Request Impractical RPV Rx Coolant System Welds, Due March 1, 2023 (Email) ML23017A2232023-01-13013 January 2023 Request for Additional Information (RAI) Issuance for McGuire Unit 1 Steam Generator Tube Inspection Report (Email) ML22175A0162022-06-24024 June 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22102A2962022-04-13013 April 2022 Request for Withholding Information from Public Disclosure Response to Request for Additional Information ML22063B1782022-03-0909 March 2022 Request for Additional Information Regarding LAR for Revision to the Conditional Exemption of the End of Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) NON-PROPRIETARY ML22010A0732022-01-0606 January 2022 50.59 Inspection Information Request ML21354A8612021-12-15015 December 2021 NRR E-mail Capture - Request for Additional Information - Duke Fleet Request RA-19-0352 - Alternative for RPV Closure Stud Exams (L-2020-LLR-0156) ML21267A2782021-09-23023 September 2021 50.59 Inspection Information Request ML21252A0532021-09-0808 September 2021 NRR E-mail Capture - Formal Release of Rais, 30 Day Response, Mcguire Relief Request, Ref: Later Edition Addenda ASME Code, Section XI, 50.55a(g)(4)(iv) ML21103A0542021-04-13013 April 2021 NRR E-mail Capture - Extension to Request for Additional Information AMS Topical Report AMS-TR-0720R1 ML21067A6742021-03-0505 March 2021 NRR E-mail Capture - Final Request for Additional Information AMS Topical Report AMS-TR-0720R1 ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML21020A0682021-01-20020 January 2021 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000369/2021011 and 05000370/2021011) and Request for Information (RFI) ML20346A0212020-12-10010 December 2020 NRR E-mail Capture - Formal Release of RAIs - License Amendment to Change TS 3.8.1 Due Jan. 29, 2021 ML20323A4072020-11-18018 November 2020 NRR E-mail Capture - Request for Additional Information - Brunswick License Exemption Request from 10CFR73 Annual Force on Force Exercise Requirements (EPIC L-2020-LLE-0180) ML20216A3512020-08-0303 August 2020 Mcquire U-1 ISI RFI ML20101L3132020-04-10010 April 2020 Notification of Inspection and Request for Information ML20071D0962020-03-0505 March 2020 NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station Unit 1 Delay in Update of the Code of Record for in Service Inspections ML20050D3382020-02-21021 February 2020 Letter RAI 1 MAGNASTOR-Catawba and McGuire Exemptions with Enclosure ML19354B6372020-01-0707 January 2020 Exemption Request for NAC Magnastor Cask Loaded to Incorrect Helium Backfill Density Request for Additional Information ML19011A1372019-01-10010 January 2019 NRR E-mail Capture - Duke Energy Fleet RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML19007A3422018-12-21021 December 2018 NRR E-mail Capture - Duke Energy Fleet Draft RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML18352A8052018-12-18018 December 2018 NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - MRP-227 Review ML18306A9372018-11-0202 November 2018 NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - Esps LAR ML18285A0812018-10-11011 October 2018 NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - TORMIS LAR RA-18-0011, Response to Request for Supplemental Information Regarding Duke Energy'S Response to GL 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2018-05-30030 May 2018 Response to Request for Supplemental Information Regarding Duke Energy'S Response to GL 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools ML18138A4662018-05-18018 May 2018 NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - TORMIS LAR ML18088B2822018-03-29029 March 2018 Requalification Program Inspection - McGuire Nuclear Station ML18057A2182018-02-23023 February 2018 Enclosurequest for Additional Information (Letter to A. Zaremba Request for Additional Information for Review of Duke Energy'S Decommissioning Funding Plan Update) ML17331B1492017-11-21021 November 2017 NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - Nsws One-Time LAR (CACs MG0242 and MG0243, EPID L-2017-LLA-0299) ML17317B0932017-11-13013 November 2017 NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - Irlt (CACs MF9020 and MF9021; EPID L-2016-LLA-0032) ML17230A1512017-08-15015 August 2017 Notification of Inspection of Inspection and Request for Information ML17192A4842017-07-11011 July 2017 NRR E-mail Capture - Duke Energy Fleet RAIs Alternative for Reactor Pressure Vessel Flange Threads Examination (MF9513 to MF9521) ML17135A0322017-05-12012 May 2017 NRR E-mail Capture - Request for Additional Information - McGuire TSTF-197 ML17114A4992017-04-17017 April 2017 Emergency Preparedness Inspection and Request for Information ML16302A1122016-11-0404 November 2016 Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program (CAC Nos. MF2934 and MF2935) MNS-16-077, Responding to Request for Additional Information Related to License Amendment Request to Implement a Risk-informed Performance-Based Fire Protection Program2016-09-29029 September 2016 Responding to Request for Additional Information Related to License Amendment Request to Implement a Risk-informed Performance-Based Fire Protection Program ML16228A2612016-08-15015 August 2016 Email - McGuire Unit No. 1: Request for Additional Informati- Relief Request 16-MN-003 Alternative to Defect Removal Prior to Performing Temporary Repair Activities on Three-Inch-Diameter Nuclear Service Water System Piping. ML16194A2862016-07-12012 July 2016 E-Mail - Mcguirai Ice Condenser Door Position Alternate Verification, (ML16089A228) CAC Nos. MF7526 and MF7527 ML16175A0222016-07-12012 July 2016 Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program ML16014A6882016-01-20020 January 2016 Request for Additional Information Regarding License Amendment Request to Revise Emergency Action Level Scheme ML15348A2602015-12-17017 December 2015 Request for Additional Information Regarding License Amendment Request to Use an Alternative Fission Gas Gap Release Fraction ML15320A3862015-11-19019 November 2015 RAI LAR to Adopt TSTF-523 ML15314A3592015-11-10010 November 2015 Duke Energy Draft RAIs Request to Adopt TSTF-523 (CAC Nos. MF6413-MF6422) ML15314A3562015-11-10010 November 2015 E-mail from J. Whited to A. Zaremba Duke Energy Draft RAIs License Amendment Request to Adopt TSTF-523 (CAC Nos. MF6413-MF6422) ML15289A5552015-10-26026 October 2015 Request for Additional Information Regarding License Amendment Request Nuclear Service Water System Allowed Outage Time Extension 2024-07-15
[Table view] |
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February 10, 2009 Mr. Bruce H. Hamilton Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078
SUBJECT:
MCGUIRE NUCLEAR STATION, UNITS 1 AND 2, REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING PROPOSED LICENSE AMENDMENT REQUEST FOR IMPLEMENTATION OF ALTERNATIVE SOURCE TERM (TAC NOS. MD8400 AND MD8401)
Dear Mr. Hamilton:
By letter dated March 20, 2008, Duke Energy Carolinas, LLC (Duke) requested an amendment to the McGuire Nuclear Station, Units 1 and 2 (McGuire 1 and 2) Facility Operating Licenses.
The amendment request proposed to revise the McGuire 1 and 2 licensing basis by adopting the Alternative Source Term (AST) radiological analysis methodology for the loss-of-coolant accident. By electronic mail message dated October 3, 2008, the U.S. Nuclear Regulatory Commission (NRC) staff sent Duke a request for additional information (RAI) with respect to the subject license amendment application. By letter dated December 17, 2008, Duke responded to this RAI. Based on this response, the NRC staff has concluded that an additional RAI is needed in order to complete its review. Based on our telephone conversation of January 29, 2008, the NRC staff understands that you will respond to this RAI by February 13, 2009.
Sincerely,
/RA/
Jon Thompson, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370
Enclosure:
Request for Additional Information cc w/encl: Distribution Via ListServ
February 10, 2009 Mr. Bruce H. Hamilton Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078
SUBJECT:
MCGUIRE NUCLEAR STATION, UNITS 1 AND 2, REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING PROPOSED LICENSE AMENDMENT REQUEST FOR IMPLEMENTATION OF ALTERNATIVE SOURCE TERM (TAC NOS. MD8400 AND MD8401)
Dear Mr. Hamilton:
By letter dated March 20, 2008, Duke Energy Carolinas, LLC (Duke) requested an amendment to the McGuire Nuclear Station, Units 1 and 2 (McGuire 1 and 2) Facility Operating Licenses.
The amendment request proposed to revise the McGuire 1 and 2 licensing basis by adopting the Alternative Source Term (AST) radiological analysis methodology for the loss-of-coolant accident. By letter dated October 3, 2008, the U.S. Nuclear Regulatory Commission (NRC) staff sent Duke a request for additional information (RAI) with respect to the subject license amendment application. By letter dated December 17, 2008, Duke responded to this RAI.
Based on this response, the NRC staff has concluded that an additional RAI is needed in order to complete its review. Based on our telephone conference of January 29, 2008, the NRC staff understands that you will respond to this RAI by February 13, 2009.
Sincerely,
/RA/
Jon Thompson, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370
Enclosure:
Request for Additional Information cc w/encl: Distribution Via ListServ Distribution:
PUBLIC RidsNrrDorlLpl2-1Resource LPL2-1 R/F RidsOgcRpResource RidsNrrLAMOBrienResource RidsAcrsAcnw_MailCTRResource RidsNrrPMJStangResource RidsRgn2MailCenterResource RidsNrrDorlDprResource RidsNrrDraAadbRTaylorResource RidsNrrDraAadbLBrown Accession Number: ML090410639 *RAI input sent by letter dated 1/30/09 ML090290181 OFFICE NRR/LPL2-1/PM NRR/LP2-1/LA NRR/AADB/BC NRR/LPL2-1/BC NAME JThompson MOBrien RTaylor* MWong DATE 2/5/2009 2/9/2009 1/30/2009 2/10/2009 OFFICIAL RECORD COPY
REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING PROPOSED LICENSE AMENDMENT REQUEST FOR IMPLEMENTATION OF ALTERNATIVE SOURCE TERM MCGUIRE NUCLEAR STATION, UNITS 1 AND 2
- 1. Section C.3.4 of Regulatory Guide (RG) 1.194, Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants, states that If the distance to the receptor is less than about 10 meters, the ARCON96 code and the procedures in Regulatory Position 4 should not be used to assess /Q values. These situations will need to be addressed on a case-by-case basis. (Regulatory Positions 4.1 to 4.3 of RG 1.194 are based on Murphy-Campe and Standard Review Plan Chapter 6.4).
With regard to the calculation of /Q values for releases from the main steam safety valves on the outboard doghouse (MSSVout), please provide a case-specific analysis that either recalculates the /Q values, or that quantitatively demonstrates that the magnitude of the MSSVout values listed in Table B-3 of Appendix D of your response sent by letter dated December 17, 2008, are bounded by dilution effects resulting from case-specific factors.
Such an analysis need not be limited to meteorological factors. For example, it may consider applicable case-specific engineering influences such as high energy flow rates, thermal buoyancy, and effects of steam flashing to atmospheric conditions, but should account for temporal changes and resultant dilution effects throughout the accident.
- 2. Based on a January 15, 2009, telephone conference between Duke and NRC staff, it is the NRC staffs understanding that Duke no longer requests approval of /Q values associated with the reactor building surface. Please confirm that this is the case.
- 3. Some of the locations identified in Figure 1 of Appendix B of your response sent by letter dated December 17, 2008, appear to be at different distances and/or directions than those listed in Table B-2 of Appendix D of your response. Please provide one or more additional figures with higher resolution which clearly highlight all release and receptor locations and from which distance, height and direction inputs can be reasonably approximated. When both an arc direction and a straight-line direction could apply, please clarify whether calculations were made for both cases and the limiting resultant /Q values were listed in Table B-3 of Appendix D.
- 4. Question 6 of your response sent by letter dated December 17, 2008, discusses the control room air intake locations and auxiliary building roof elevation. Please clarify whether the heights of the control room air intakes are 3.6 meters above plant grade. Were all of the source and receptor values input into the ARCON96 computer code with respect to their height above plant grade? If the height of the auxiliary building roof was factored into the ARCON96 inputs, how was this done and to which release locations does it apply?
Table B-2 of Appendix D of your response sent by letter dated December 17, 2008, lists non-zero initial sigma-y and sigma-z values for each of the following postulated release locations:
Enclosure
equipment hatch (EQ),
fuel building (FUEL),
inboard doghouse (NDOG),
inboard doghouse plus steam and feedwater line penetrations (VNDOG) outboard doghouse (ODOG),
outboard doghouse plus steam and feedwater line penetrations (VODOG), and reactor building surface (RX).
The NRC staff notes that the diffusion models incorporated in ARCON96 are Gaussian models that assume that the release is from a point source. When using ARCON96 for a point source, the initial sigma y and sigma z are both zero, which are the default values.
Input of a non-zero initial sigma value identifies the release as a diffuse source. Since ARCON96 is not able to directly calculate atmospheric dispersion factors for non-point sources, it uses each non-zero initial sigma value to determine the distance from the center of the real source to a virtual point source upwind of the real source.
Regulatory Position 3.2.4.5 of RG 1.194, states that the height and width of the area source may be taken as the maximum vertical and horizontal dimensions perpendicular to the line of sight from the source center to the control room intake. These dimensions are used to calculate the initial sigma values which ARCON96 uses to calculate upwind virtual point sources. Regulatory Position 3.2.4.8, which discusses large louvered panels or large openings, states that application of the diffuse area source model would be appropriate when (1) the release rate from the building interior is essentially equally dispersed over the entire surface of the panel or opening and (2) assumptions of mixing, dilution, and transport within the building necessary to meet condition 1 are supported by the interior building arrangement.
Other than for the reactor building surface, please provide drawings showing the orientation of release with respect to the control room intake, describe the physical characteristics resulting in a diffuse release (e.g., louvered panel, array of vents) and further justify that it is appropriate to model each of the sources using the initial sigma-y and sigma-z values and distances and directions listed in Table B-2 of Appendix D of your response sent by letter dated December 17, 2008. Confirm that the other criteria discussed above have been met and that a release through another penetration (e.g., a single vent) would not result in more limiting /Q values than from the diffuse source.