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MONTHYEARML11152A1482011-05-19019 May 2011 Core Operating Limits Report, Cycle 21 Project stage: Request ML1126303712011-10-24024 October 2011 Request for Additional Information Regarding Cycle 12 Core Operating Limits Report Project stage: RAI ML11342A1222011-11-30030 November 2011 Response to Request for Additional Information Regarding the Cycle 21 Core Operating Limits Report Project stage: Response to RAI ML12025A2252012-01-18018 January 2012 Response to Request for Additional Information Regarding the Cycle 21 Core Operating Limits Report Project stage: Response to RAI ML12025A2262012-01-18018 January 2012 Calculation 32-9149958-001, Millstone, Unit 2 Cycle 21 Peaking Factor Uncertainty Analysis for Ici Detector Misalignment, (Non-Proprietary) Project stage: Other ML1208304582012-04-10010 April 2012 Request for Withholding Information from Public Disclosure for Millstone Power Station, Unit No. 2 Project stage: Withholding Request Acceptance ML12129A2002012-05-0101 May 2012 Supplement to Response to Request for Additional Information Regarding the Cycle 21 Core Operating Limits Report Project stage: Supplement ML1213709632012-05-22022 May 2012 Review of the Core Operating Limits Report (Colr), Cycle 21 Project stage: Approval 2012-01-18
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MONTHYEARML24030A7522024-01-30030 January 2024 Technical Specification Bases Pages IR 05000336/20234022024-01-30030 January 2024 Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only) ML23341A0172024-01-12012 January 2024 Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures IR 05000336/20234402024-01-11011 January 2024 Special Inspection Report 05000336/2023440 and 05000423/2023440 (Cover Letter Only) ML24004A1052024-01-0404 January 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000336/2024010 & 05000423/2024010 ML23361A0942023-12-21021 December 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies and Core Operating Limits Report . ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23361A0312023-12-20020 December 2023 Intent to Pursue Subsequent License Renewal ML23352A0202023-12-18018 December 2023 Senior Reactor and Reactor Operator Initial License Examinations ML23334A2242023-11-30030 November 2023 Request for Exemption from Enhanced Weapons Firearms Background Checks, and Security Event Notifications Implementation ML23324A4222023-11-20020 November 2023 Reactor Vessel Internals Inspections Aging Management Program Submittal Related to License Renewal Commitment 13 ML23324A4302023-11-20020 November 2023 Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15 ML23317A2702023-11-13013 November 2023 Core Operating Limits Report, Cycle 23 IR 05000336/20230032023-11-0606 November 2023 Integrated Inspection Report 05000336/2023003 and 05000423/2023003 ML23298A1652023-10-26026 October 2023 Requalification Program Inspection IR 05000336/20234202023-10-0404 October 2023 Security Inspection Report 05000336/2023420 and 05000423/2023420 ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes ML23226A0052023-09-26026 September 2023 Issuance of Amendment No. 287 Supplement to Spent Fuel Pool Criticality Safety Analysis IR 05000245/20230012023-09-19019 September 2023 Safstor Inspection Report 05000245/2023001 IR 05000336/20230102023-09-0808 September 2023 Commercial Grade Dedication Report 05000336/2023010 and 05000423/2023010 IR 05000336/20230052023-08-31031 August 2023 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Report 05000336/2023005 and 05000423/2023005) ML23248A2132023-08-30030 August 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise the Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature. ML23242A0142023-08-30030 August 2023 Operator Licensing Examination Approval ML23223A0552023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies, and COLR Related to Framatome Gaia Fuel ML23223A0482023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Use Framatome Small Break and Realistic Large Break LOCA Evaluation Methodologies for Establishing COLR Limits IR 05000336/20230022023-08-0909 August 2023 Integrated Inspection Report 05000336/2023002 and 05000423/2023002 ML23188A0432023-07-31031 July 2023 Authorization and Safety Evaluation for Alternative Request No. IR-04-11 ML23208A0922023-07-26026 July 2023 Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response ML23188A0202023-07-26026 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23207A1102023-07-26026 July 2023 NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations IR 05000336/20234012023-07-17017 July 2023 Material Control and Accounting Program Inspection Report 05000336/2023401 and 05000423/2023401 - (Cover Letter Only) ML23175A0052023-07-12012 July 2023 Alternative Request P-07 for Pump Periodic Verification Testing Program for Containment Recirculation Spray System Pumps ML23193A8562023-06-28028 June 2023 Submittal of Updates to the Final Safety Analysis Reports ML23178A1682023-06-26026 June 2023 2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML23153A1732023-06-16016 June 2023 Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement ML23151A0742023-06-12012 June 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23159A2202023-06-0808 June 2023 Associated Independent Spent Fuel Storage Installation Revision to Emergence Plan - Report of Changes IR 07200047/20234012023-06-0808 June 2023 NRC Independent Spent Fuel Storage Installation Security Inspection Report No. 07200047/2023401 2024-01-04
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Dominion Nucear Conneetieut, Ie.
5000 Dominion Boulevard, Glen Allen, Virginia 23060 Web Address: www.dom.com January 18, 2012 U. S. Nuclear Regulatory Commission Serial No. 11-620A Attention: Document Control Desk NSSL/WDC RO Washington, DC 20555 Docket No. 50-336 License No. DPR-65 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING THE CYCLE 21 CORE OPERATING LIMITS REPORT (TAC NO. ME6365)
Dominion Nuclear Connecticut, Inc. (DNC) submitted the Millstone Power Station Unit 2 (MPS2) Cycle 21 Core Operating Limits Report (COLR) to the Nuclear Regulatory Commission (NRC) in a letter dated May 19, 2011. The COLR includes the values of cycle-specific parameter limits and is submitted to the NRC for information. In a letter dated October 24, 2011, the NRC transmitted a request for additional information (RAI) to DNC related to the MPS2 Cycle 21 COLR. In a letter dated November 30, 2011, DNC responded to the RAIs. In RAI Question 4, the NRC requested a proprietary AREVA engineering calculation which DNC agreed to provide by January 31, 2012.
The proprietary AREVA engineering calculation is provided in Attachment 1. The non-proprietary version of the calculation is provided in Attachment 2. It is respectfully requested that Attachment 1 be withheld from public disclosure in accordance with 10 CFR 2.390. The AREVA application for withholding and affidavit is provided in .
If you have any questions regarding this submittal, please contact Wanda Craft at (804) 273-4687.
Sincerely, L. N. Hartz Vice President - Nuclear ipport Services Attachments:
- 1. Millstone Unit 2 Cycle 21 Peaking Factor Uncertainty Analysis for ICI Detector Misalignment (Proprietary)
- 2. Millstone Unit 2 Cycle 21 Peaking Factor Uncertainty Analysis for ICI Detector Misalignment (Non-Proprietary)
- 3. AREVA Affidavit 7AObI
Serial No. 11-620A Docket No. 50-336 RAI Response for MPS2 Cycle 21 COLR Page 2 of 2 Commitments made in this letter:
- 1. None cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 C. J. Sanders Project Manager - Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08-B3 Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station