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| | issue date = 10/24/2011 | | | issue date = 10/24/2011 |
| | title = Request for Additional Information Regarding Cycle 12 Core Operating Limits Report | | | title = Request for Additional Information Regarding Cycle 12 Core Operating Limits Report |
| | author name = Sanders C J | | | author name = Sanders C |
| | author affiliation = NRC/NRR/DORL/LPLI-2 | | | author affiliation = NRC/NRR/DORL/LPLI-2 |
| | addressee name = Heacock D A | | | addressee name = Heacock D |
| | addressee affiliation = Dominion Nuclear Connecticut, Inc | | | addressee affiliation = Dominion Nuclear Connecticut, Inc |
| | docket = 05000336 | | | docket = 05000336 |
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| ==Dear Mr. Heacock:== | | ==Dear Mr. Heacock:== |
| By letter dated May 19, 2011 (Agencywide Documents Access and Management System Accession No. ML 11152A 148), Dominion Nuclear Connecticut, Inc. (DNC or the licensee) submitted the Millstone Power Station, Unit No.2 (MPS2) Cycle 21 Core Operating Limits Report in accordance with the MPS2 Technical Specifications. | | By letter dated May 19, 2011 (Agencywide Documents Access and Management System Accession No. ML11152A148), Dominion Nuclear Connecticut, Inc. (DNC or the licensee) submitted the Millstone Power Station, Unit No.2 (MPS2) Cycle 21 Core Operating Limits Report in accordance with the MPS2 Technical Specifications. |
| The U.S. Nuclear Regulatory Commission staff has reviewed the information submitted by the licensee, and based on this review, determined that additional information is required to complete the review. The draft questions were sent to Mr. William Bartran, of your staff, to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. | | The U.S. Nuclear Regulatory Commission staff has reviewed the information submitted by the licensee, and based on this review, determined that additional information is required to complete the review. The draft questions were sent to Mr. William Bartran, of your staff, to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. |
| On October 18, 2011, Ms. Wanda Craft, of your staff, agreed that you would provide a response by November 30,2011. If you have any questions regarding this matter, please contact me at 301-415-1603. | | On October 18, 2011, Ms. Wanda Craft, of your staff, agreed that you would provide a response by November 30,2011. If you have any questions regarding this matter, please contact me at 301-415-1603. |
| 7:7'1. Carleen danders, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. | | 7:7'1. Carleen danders, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. |
| Request for Additional cc Distribution via REQUEST FOR ADDITIONAL INFORMATION CORE OPERATING LIMITS REPORT DOMINION NUCLEAR CONNECTICUT, INC. MILLSTONE POWER STATION, UNIT NO.2 DOCKET NO. 50-336 By letter dated May 19, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 11152A 148), Dominion Nuclear Connecticut, Inc. (DNC or the licensee) submitted the Millstone Power Station, Unit No.2 (MPS2) Cycle 21 Core Operating Limits Report (COLR) in accordance with the MPS2 Technical Specifications (TSs). Generic Letter (GL) 88-16, "Removal of Cycle-Specific Parameter Limits from Technical Specifications," provided guidance to licensee's on removing cycle-specific parameters from the TSs and placing them into a formal report to be submitted to the U.S. Nuclear Regulatory Commission (NRC). By letter dated October 12,1990 (ADAMS Accession No. ML012890108), the NRC approved an amendment for MPS2 to remove the cycle-specific parameter limits from the TSs and placed the limits in the COLR. In accordance with GL 88-16, the COLR "includes the values of cycle-specific parameter limits that have been established using an NRC-approved methodology and consistent with all applicable limits of the safety analysis," and shall be submitted to the NRC staff for information. | | Request for Additional cc Distribution via REQUEST FOR ADDITIONAL INFORMATION CORE OPERATING LIMITS REPORT DOMINION NUCLEAR CONNECTICUT, INC. MILLSTONE POWER STATION, UNIT NO.2 DOCKET NO. 50-336 By letter dated May 19, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11152A148), Dominion Nuclear Connecticut, Inc. (DNC or the licensee) submitted the Millstone Power Station, Unit No.2 (MPS2) Cycle 21 Core Operating Limits Report (COLR) in accordance with the MPS2 Technical Specifications (TSs). Generic Letter (GL) 88-16, "Removal of Cycle-Specific Parameter Limits from Technical Specifications," provided guidance to licensee's on removing cycle-specific parameters from the TSs and placing them into a formal report to be submitted to the U.S. Nuclear Regulatory Commission (NRC). By letter dated October 12,1990 (ADAMS Accession No. ML012890108), the NRC approved an amendment for MPS2 to remove the cycle-specific parameter limits from the TSs and placed the limits in the COLR. In accordance with GL 88-16, the COLR "includes the values of cycle-specific parameter limits that have been established using an NRC-approved methodology and consistent with all applicable limits of the safety analysis," and shall be submitted to the NRC staff for information. |
| MPS2 TSs state the core operating limits for the linear heat rate shall be established and documented in the COLR. The MPS2 TSs further state that the analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those methods described in the documents referenced in MPS2 TS 6.9.1.8b. | | MPS2 TSs state the core operating limits for the linear heat rate shall be established and documented in the COLR. The MPS2 TSs further state that the analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those methods described in the documents referenced in MPS2 TS 6.9.1.8b. |
| In the May 19, 2011, letter DNC states that there is an U[a]ddition of a penalty factor to account for the impact of the offset incore instrument (ICI) detectors on the linear heat rate measurement," for Cycle 21 at MPS2. In order to complete its review of the MPS2 Cycle 21 COLR, the NRC staff needs the following additional information: Please provide a detailed description of the methodology used to determine the linear heat rate measurement. | | In the May 19, 2011, letter DNC states that there is an U[a]ddition of a penalty factor to account for the impact of the offset incore instrument (ICI) detectors on the linear heat rate measurement," for Cycle 21 at MPS2. In order to complete its review of the MPS2 Cycle 21 COLR, the NRC staff needs the following additional information: Please provide a detailed description of the methodology used to determine the linear heat rate measurement. |
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| ==Dear Mr. Heacock:== | | ==Dear Mr. Heacock:== |
| By letter dated May 19, 2011 (Agencywide Documents Access and Management System Accession No. ML 11152A 148), Dominion Nuclear Connecticut, Inc. (DNC or the licensee) submitted the Millstone Power Station, Unit No.2 (MPS2) Cycle 21 Core Operating Limits Report in accordance with the MPS2 Technical Specifications. | | By letter dated May 19, 2011 (Agencywide Documents Access and Management System Accession No. ML11152A148), Dominion Nuclear Connecticut, Inc. (DNC or the licensee) submitted the Millstone Power Station, Unit No.2 (MPS2) Cycle 21 Core Operating Limits Report in accordance with the MPS2 Technical Specifications. |
| The U.S. Nuclear Regulatory Commission staff has reviewed the information submitted by the licensee, and based on this review, determined that additional information is required to complete the review. The draft questions were sent to Mr. William Bartron, of your staff, to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. | | The U.S. Nuclear Regulatory Commission staff has reviewed the information submitted by the licensee, and based on this review, determined that additional information is required to complete the review. The draft questions were sent to Mr. William Bartron, of your staff, to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. |
| On October 18, 2011, Ms. Wanda Craft, of your staff, agreed that you would provide a response by November 30,2011. If you have any questions regarding this matter, please contact me at 301-415-1603. | | On October 18, 2011, Ms. Wanda Craft, of your staff, agreed that you would provide a response by November 30,2011. If you have any questions regarding this matter, please contact me at 301-415-1603. |
Letter Sequence RAI |
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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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Category:Letter
MONTHYEARML24289A0152024-10-21021 October 2024 Review of the Fall 2023 Steam Generator Tube Inspection Report 05000423/LER-2024-001, Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary2024-10-14014 October 2024 Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary IR 05000336/20244022024-10-0808 October 2024 Security Baseline Inspection Report 05000336/2024402 and 05000423/2024402 (Cover Letter Only) ML24281A1102024-10-0707 October 2024 Requalification Program Inspection 05000423/LER-2023-006-02, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-09-26026 September 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24260A2192024-09-16016 September 2024 Decommissioning Trust Fund Disbursement - Revision to Previous Thirty-Day Written Notification ML24260A1952024-09-16016 September 2024 Response to Request for Additional Information Regarding Proposed Amendment to Support Implementation of Framatome Gaia Fuel ML24248A2272024-09-0404 September 2024 Operator Licensing Examination Approval ML24240A1532024-09-0303 September 2024 Summary of Regulatory Audit Supporting the Review of License Amendment Request for Implementation of Framatome Gaia Fuel IR 05000336/20240052024-08-29029 August 2024 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Reports 05000336/2024005 and 05000423/2024005 IR 05000336/20240022024-08-13013 August 2024 Integrated Inspection Report 05000336/2024002 and 05000423/2024002 ML24221A2872024-08-0808 August 2024 Independent Spent Fuel Storage Installation (ISFSI) - Submittal of Cask Registration for Spent Fuel Storage IR 05000336/20244412024-08-0606 August 2024 Supplemental Inspection Report 05000336/2024441 and 05000423/2024441 and Follow-Up Assessment Letter (Cover Letter Only) ML24212A0742024-08-0505 August 2024 Request for Withholding Information from Public Disclosure - Millstone Power Station, Unit No. 3, Proposed Alternative Request IR-4-13 to Support Steam Generator Channel Head Drain Modification ML24211A1712024-07-25025 July 2024 Associated Independent Spent Fuels Storage Installation, Revision to Emergency Plan - Report of Change IR 05000336/20244032024-07-22022 July 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403 IR 05000336/20245012024-07-0101 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000336/2024501 and 05000423/2024501 ML24180A0932024-06-28028 June 2024 Readiness for Additional Inspection: EA-23-144 IR 05000336/20240102024-06-26026 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000336/2024010 and 05000423/2024010 ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 IR 05000336/20244402024-06-24024 June 2024 Final Significance Determination for Security-Related Greater than Green Finding(S) with Assessment Follow-up; IR 05000336/2024440 and 05000423/2024440 and Notice of Violation(S), NRC Investigation Rpt 1-2024-001 (Cvr Ltr Only) ML24176A2622024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 ML24176A1782024-06-20020 June 2024 Update to the Final Safety Analysis Report ML24281A2072024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 (Redacted Version) ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24280A0012024-06-20020 June 2024 Update to the Final Safety Analysis Report (Redacted Version) 05000336/LER-2024-001, Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications2024-06-10010 June 2024 Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24165A1292024-06-0505 June 2024 ISFSI, 10 CFR 50.59 Annual Change Report for 2023 Annual Regulatory Commitment Change Report for 2023 ML24128A2772024-06-0404 June 2024 Issuance of Amendment No. 290 to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and Core Operating Limits Report for Use of Framatome Gaia Fuel (EPID L-2023-LLA-0074) (Non-Proprietary) ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24110A0562024-05-21021 May 2024 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2023-LLE-0013) (Letter) ML24109A0032024-05-21021 May 2024 Issuance of Amendment No. 289 to Revise Technical Specifications to Use Framatome Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limit (EPID L-2023-LLA-0065) (Non-Proprietary) ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report ML24141A2432024-05-20020 May 2024 Response to Request for Additional Information Regarding Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment No. 15 05000423/LER-2023-006-01, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-20020 May 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications IR 05000336/20240012024-05-14014 May 2024 Integrated Inspection Report 05000336/2024001 and 05000423/2024001 and Apparent Violation ML24123A2042024-05-0202 May 2024 Pre-Decisional Replay to EA-23-144 05000423/LER-2023-006, Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-0202 May 2024 Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications IR 05000336/20244012024-04-30030 April 2024 Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only) ML24123A1222024-04-30030 April 2024 Inservice Inspection Program - Owners Activity Report, Refueling Outage 22 ML24116A0452024-04-25025 April 2024 Special Inspection Follow-Up Report 05000336/2024440 and 05000423/2024440 and Preliminary Finding(S) of Greater than Very Low Significance and NRC Investigation Report No. 1-2024-001 (Cover Letter Only) ML24116A1742024-04-24024 April 2024 Annual Radiological Environmental Operating Report ML24114A2662024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report ML24103A0202024-04-22022 April 2024 Summary of Regulatory Audit in Support of License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits ML24106A2032024-04-15015 April 2024 2023 Annual Environmental Operating Report ML24088A3302024-04-0404 April 2024 Regulatory Audit Plan in Support of License Amendment Request to Implement Framatome Gaia Fuel IR 05000336/20240112024-04-0101 April 2024 Comprehensive Engineering Team Inspection - Inspection Report 05000336/2024011 and 05000423/2024011 ML24093A1022024-04-0101 April 2024 Alternative Request IR-4-13, Proposed Alternative Request to Support Steam Genera Tor Channel Head Drain Modification 2024-09-04
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24213A2602024-07-31031 July 2024 Request for Additional Information LAR to Support Implementation of Framatome Gaia Fuel IR 05000336/20244032024-07-22022 July 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403 ML24113A2502024-04-22022 April 2024 Request for Additional Information (e-mail 4/22/2024) License Renewal Commitment for Aging Management Program of Alloy 600 Components ML24065A3112024-03-0505 March 2024 Request for Additional Information (Redacted) (03/05/2025 E-mail from R. Guzman to S. Sinha) Framatome Gaia Fuel LOCA LAR ML23318A0952023-11-14014 November 2023 Request for Additional Information (E-mail Dated 11/14/2023) LAR to Revise TSs Related to Framatome Gaia Fuel ML23199A2832023-07-18018 July 2023 Request for Additional Information (E-mail Dated 7/18/2023) LAR to Revise the Pressure-Temperature Limits ML23171B0522023-06-20020 June 2023 NRR E-mail Capture - RAI for Review of Appendix F to DOM-NAF-2-P (Redacted) ML23089A1882023-03-29029 March 2023 Request for Additional Information (E-mail Dated 3/29/2023) Spring 2022 Steam Generator Tube Inspection Report ML23073A1802023-03-14014 March 2023 Notification of Commercial Grade Dedication Inspection (05000336/2023010 and 05000423/2023010) and Request for Information ML22251A1292022-09-0909 September 2022 Request for Additional Information Related to Response to Generic Letter 2004-04 ML22242A0452022-08-23023 August 2022 NRR E-mail Capture - Dominion GL 04-02 Response Draft RAIs (L-2017-LRC-0000) ML21225A5022021-08-13013 August 2021 Request for Additional Information for North Anna Power Station, Units 1 and 2, Surry Power Station, Units 1 and 2, and Millstone Power Station, Units 2 and 3, Appendix E of Fleet Report Com-Naf-2 (EPID:L02021-LLT-0000) Public Version ML21195A2442021-07-13013 July 2021 NRR E-mail Capture - Draft RAI Appendix E to Topical Report DOM-NAF-2 Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML21182A2902021-07-0101 July 2021 7/1/2021 E-mail - Request for Additional Information Alternative Frequency to Supplemental Valve Position Verification Testing Requirements ML21112A3082021-04-22022 April 2021 Request for Additional Information (E-mail Dated 4/22/2021) License Amendment Request for Measurement Uncertainty Recapture Power Uprate ML21105A1152021-04-15015 April 2021 Request for Additional Information (e-mail Dated 4/15/2021) Proposed LAR for Addition of Analytical Methodology to the Core Operating Limits Report for a LBLOCA ML21078A0332021-03-18018 March 2021 NRR E-mail Capture - Millstone Power Station, Unit 2 - Request for Additional Information - Proposed LAR to Revise TSs for Steam Generator Inspection Frequency ML21076A4622021-03-17017 March 2021 NRR E-mail Capture - Draft RAI for Versatile Internals and Component Program for Reactors Vipre Code Review (L-2021-LLT-0000) ML21077A1652021-02-26026 February 2021 (02/26/2021 E-mail) Draft Request for Additional Information LAR to Revise Technical Specifications for Steam Generator Inspection Frequency ML21034A5762021-02-0303 February 2021 Request for Additional Information (e-mail Dated 1/3/2021) Alternative Request RR-05-06 Inservice Inspection Interval Extension for Steam Generator Weld Inspections ML20246G5612020-09-0202 September 2020 Request for Additional Information (E-mail Dated 9/2/2020) License Amendment Request for a One-Time Deferral of the Steam Generator Inspections ML20244A2902020-08-31031 August 2020 Request for Additional Information (E-mail Dated 8/31/2020) License Amendment Request to Revise Battery Surveillance Requirements ML20231A7172020-08-18018 August 2020 Request for Additional Information (e-mail Dated 8/18/2020) License Amendment Request to Revise TS Table 3.3-11 Accident Monitoring Instrumentation ML20184A0052020-07-0202 July 2020 Request for Additional Information (E-mail Dated 7/2/2020) Relief Request IR-3-33 for Limited Coverage Examiniations ML20075A0322020-03-15015 March 2020 Request for Additional Information (E-mail Dated 3/15/2020) Alternative Request IR-4-03 for Use of an Alternative Non-Code Methodology to Demonstrate Structural Integrity ML20050F9212020-02-19019 February 2020 Request for Additional Information (E-mail Dated 2/19/2020) Proposed LAR to Revise TS 3.8.1.1, AC Sources Operating ML20023D0372020-01-23023 January 2020 Request for Additional Information (E-mail Dated 1/23/2020) Proposed LAR to Revise TS 3.8.1.1, AC Sources Operating ML19361A0382019-12-23023 December 2019 12/23/19 E-mail from R.Guzman to S. Sinha - Draft Request for Additional Information Planned Audit of LAR to Revise TS 3.8.1.1 ML19277B9082019-10-0707 October 2019 Supplemental Information Needed for Acceptance of Requested Licensing Action Extension of Technical Specification 3.8.1.1, A.C. Sources - Operating, Allowed Outage Time ML19248D7552019-09-0505 September 2019 Request for Additional Information Via E-mail from R.Guzman to S. Sinha Proposed License Amendment Request to Adopt 10 CFR 50.69 ML19169A0962019-06-17017 June 2019 NRR E-mail Capture - Request for Additional Information Emergency Action Level Scheme Change for Millstone Power Station - Units 1, 2, and 3, North Anna Power Station - Units 1 and 2, and Surry Power Station - Units 1 and 2 ML19162A0052019-06-10010 June 2019 NRR E-mail Capture - Draft RAIs for Dominion EAL Scheme Change ML19042A1822019-02-11011 February 2019 Request for Additional Information LAR for TS Changes to Spent Fuel Storage and New Fuel Storage, 02/11/2019 E-mail from R. Guzman to S. Sinha ML18291B3262018-10-18018 October 2018 Request for Additional Information LAR Regarding Proposed Technical Specification Changes for Spent Fuel Pool Storage and New Fuel Storage, E-mail from R.Guzman to S.Sinha ML18277A1762018-10-0404 October 2018 Request for Additional Information LAR to Revise TS Action Statement for Loss of Control Building Inlet Ventilation Rad Monitor Instrumentation Channels (e-mail from R.Guzman to M.Whitlock, EPID: L-2018-LLA-0099) ML18213A1152018-08-0101 August 2018 Request for Additional Information Alternative Request P-06 'C' Charging Pump (08/01/2018 E-mail from R. Guzman to M. Whitlock) ML18171A1532018-06-20020 June 2018 Request for Additional Information Via E-mail from R.Guzman to W.Craft Alternative Requests for Inservice Testing Program (E-mail from R.Guzman to W.Craft) (EPID: L-2018-LLR-0012-LLR-0022) ML18137A3132018-05-17017 May 2018 Request for Additional Information Via E-mail from R.Guzman to W.Craft Proposed License Amendment Request to Revise ILRT Type a and Type C Test Intervals ML17297A8472017-10-27027 October 2017 Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools (CAC No. MF9430; EPID L-2016-LRC-0001) ML17033B6142017-02-0202 February 2017 Request for Additional Information, 2017/02/02 E-mail from R.Guzman to W.Craft Proposed Alternative RR-04-24 and IR-3-30 for the Elimination of Reactor Pressure Vessel Threads in Flange Examination (CAC Nos. MF8468/MF8469) ML17005A3282017-01-0505 January 2017 MPS2 EOC-23 and MPS3 EOC-17 Steam Generator Tube Inspection Reports - Requests for Additional Information ML16260A0062016-09-16016 September 2016 2016/09/16 E-mail from R. Guzman to W. Craft Request for Additional Information - License Amendment Request Realistic Large Break Loss of Coolant Accident Analysis (MF7761) ML16267A0022016-09-12012 September 2016 2016/09/12 E-mail from R.Guzman to W.Craft Request for Additional Information - LAR to Revise ECCS TS and FSAR Ch. 14 to Remove Charging (MF7297) ML16133A3562016-05-12012 May 2016 E-mail from R. Guzman to C. Sly Request for Additional Information Supporting License Amendment Request to Remove Charging Credit ML16068A4142016-03-0808 March 2016 Request for Additional Information - Relief Request RR-04-19 Examination Cat R-A, Risk-Informed Piping Examinations (MF6569) ML16055A5302016-02-24024 February 2016 2016/02/24 E-mail from R.Guzman to W.Craft Request for Additional Information - LAR to Adopt Dominion Core Design and Safety Analysis Methods (MF6251) ML16047A1712016-02-16016 February 2016 2016/02/16 E-mail from R.Guzman to M. Whitlock Request for Additional Information - Small Break Loss of Coolant Accident Re-Analysis (MF6700) ML16043A5232016-02-12012 February 2016 Request for Additional Information 2016/02/12 E-mail from R. Guzman to M.Whitlock Relief Requests IR-3-22 and IR-3-23 (CAC Nos. MF6573 and MF6574) ML16013A4772016-01-13013 January 2016 NRR E-mail Capture - Millstone Power Station, Units 2 and 3 - Request for Additional Information License Amendment Request for Removal of Severe Line Outage Detection (Slod) from the Offsite Power System - (MF6430, MF6431) ML16011A5172016-01-11011 January 2016 NRR E-mail Capture - Millstone Power Station, Unit 3, Reactor Vessel Surveillance Capsule Withdrawal Schedule - Request for Additional Information 2024-07-31
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 October 24, 2011 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc. Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 MILLSTONE POWER STATION, UNIT NO.2 -REQUEST FOR ADDITIONAL INFORMATION REGARDING CYCLE 12 CORE OPERATING LIMITS REPORT (TAC NO. ME6365)
Dear Mr. Heacock:
By letter dated May 19, 2011 (Agencywide Documents Access and Management System Accession No. ML11152A148), Dominion Nuclear Connecticut, Inc. (DNC or the licensee) submitted the Millstone Power Station, Unit No.2 (MPS2) Cycle 21 Core Operating Limits Report in accordance with the MPS2 Technical Specifications.
The U.S. Nuclear Regulatory Commission staff has reviewed the information submitted by the licensee, and based on this review, determined that additional information is required to complete the review. The draft questions were sent to Mr. William Bartran, of your staff, to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed.
On October 18, 2011, Ms. Wanda Craft, of your staff, agreed that you would provide a response by November 30,2011. If you have any questions regarding this matter, please contact me at 301-415-1603.
7:7'1. Carleen danders, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.
Request for Additional cc Distribution via REQUEST FOR ADDITIONAL INFORMATION CORE OPERATING LIMITS REPORT DOMINION NUCLEAR CONNECTICUT, INC. MILLSTONE POWER STATION, UNIT NO.2 DOCKET NO. 50-336 By letter dated May 19, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11152A148), Dominion Nuclear Connecticut, Inc. (DNC or the licensee) submitted the Millstone Power Station, Unit No.2 (MPS2) Cycle 21 Core Operating Limits Report (COLR) in accordance with the MPS2 Technical Specifications (TSs). Generic Letter (GL) 88-16, "Removal of Cycle-Specific Parameter Limits from Technical Specifications," provided guidance to licensee's on removing cycle-specific parameters from the TSs and placing them into a formal report to be submitted to the U.S. Nuclear Regulatory Commission (NRC). By letter dated October 12,1990 (ADAMS Accession No. ML012890108), the NRC approved an amendment for MPS2 to remove the cycle-specific parameter limits from the TSs and placed the limits in the COLR. In accordance with GL 88-16, the COLR "includes the values of cycle-specific parameter limits that have been established using an NRC-approved methodology and consistent with all applicable limits of the safety analysis," and shall be submitted to the NRC staff for information.
MPS2 TSs state the core operating limits for the linear heat rate shall be established and documented in the COLR. The MPS2 TSs further state that the analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those methods described in the documents referenced in MPS2 TS 6.9.1.8b.
In the May 19, 2011, letter DNC states that there is an U[a]ddition of a penalty factor to account for the impact of the offset incore instrument (ICI) detectors on the linear heat rate measurement," for Cycle 21 at MPS2. In order to complete its review of the MPS2 Cycle 21 COLR, the NRC staff needs the following additional information: Please provide a detailed description of the methodology used to determine the linear heat rate measurement.
Is this methodology approved by the NRC, and is it described in the documents referenced in TS 6.9.1.8b? Describe the methodology used to generate a penalty factor to account for the impact of the offset ICI detectors on the linear heat rate measurement.
Is this methodology approved by the NRC, and is it described in the documents referenced in TS 6.9.1.8b? Is the impact of the offset ICI detectors on the revised acceptable operating region (Figure 2.5-1) conservative?
Is the revised penalty factor specified in item 2.5 conservative?
Enclosure
-Provide documentation (e.g. any analysis or evaluation) of the impact of the offset ICI detectors on the linear heat rate measurement. Please provide any Title 10 of the Code of Federal Regulations, Part 50.59 design change screening and/or evaluations related to the offset ICI detectors.
October 24, 2011 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc. Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 MILLSTONE POWER STATION, UNIT NO.2 -REQUEST FOR ADDITIONAL INFORMATION REGARDING CYCLE 12 CORE OPERATING LIMITS REPORT (TAC NO. ME6365)
Dear Mr. Heacock:
By letter dated May 19, 2011 (Agencywide Documents Access and Management System Accession No. ML11152A148), Dominion Nuclear Connecticut, Inc. (DNC or the licensee) submitted the Millstone Power Station, Unit No.2 (MPS2) Cycle 21 Core Operating Limits Report in accordance with the MPS2 Technical Specifications.
The U.S. Nuclear Regulatory Commission staff has reviewed the information submitted by the licensee, and based on this review, determined that additional information is required to complete the review. The draft questions were sent to Mr. William Bartron, of your staff, to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed.
On October 18, 2011, Ms. Wanda Craft, of your staff, agreed that you would provide a response by November 30,2011. If you have any questions regarding this matter, please contact me at 301-415-1603.
Sincerely, Ira/ Carleen J. Sanders, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Request for Additional cc Distribution via DISTRIBUTION:
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