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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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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PENNSYLVANIA 19406-2713 March 17, 2017
Mr. Robert Kaliszewski Deputy Commissioner for Environmental Quality Connecticut Department of Energy and Environmental Protection 79 Elm Street Hartford, CT 06106-5127
Dear Mr. Kaliszewski:
Thank you for your letter dated February 23, 2017, expressing your concerns in manufacturing irregularities identified at Areva's Creusot Forge facility and, specifically, how they pertain to Millstone Power Station Unit 2. The NRC values the cooperative agreement established between the NRC and the Governor-appointed State Liaison Officer for keeping the State
informed of NRC activities with respect to the regulatory oversight of the Millstone Power Station.
As was discussed with your staff in a briefing on February 9, 2017, the NRC is closely following the investigation of Areva and the French Nuclear Safety Authority, ASN, and there remain no safety concerns at operating US nuclear plants at this time.
With regard to the recommendations documented in your letter, the NRC acknowledges your support of Dominion's planned activities to address the issue during the planned refueling outage of Millstone Unit 2 this spring. We also acknowledge your request that any testing or analyses conducted to evaluate the susceptibility of the Millstone 2 pressurizer be independently verified by technical experts not associated with Areva. At this time, there are no known safety concerns at any U.S. nuclear operating plant for either the carbon segregation topic or the fabrication record anomalies. This is based on the NRC's knowledge of the U.S. material qualification process, preliminary structural evaluations for the carbon segregation issue, and NRC staff participation in the inspection at Creusot Forge and information received
from AREVA for the documentation fabrication record anomalies. Consequently, the NRC is not currently requiring any specific action by U.S. plant owners who have large components installed in their plants manufactured at Creusot Forge.
On March 22, 2017, the NRC will meet with Connecticut's Nuclear Energy Advisory Council (NEAC) at the Waterford Public Library to discuss our assessment of the safety performance at the Millstone Power Station for calendar year 2016. We have attached the notice of the public meeting, which can also be found in the NRC's document management system (ADAMS) or on the NRC's public website by searching for accession number ML17068A058 . Following this discussion, we will respond to questions by NEAC members and members of the public on specific performance issues at the plant and our role in ensuring safe plant operations. Staff from the NRC's Offices of Nuclear Reactor Regulation and New Reactors will be in attendance Mr. Robert Kaliszewski 2
at the meeting to answer questions pertaining to carbon segregation and fabrication record anomalies identified at Areva's Creusot Forge facility.
Finally, you requested that the NRC staff conduc t a "government to government" meeting in April 2017 to update your staff on the NRC's assessment of the applicability of manufacturing irregularities to Millstone Unit 2. Through discussions with Mr. Jeffrey Semancik, State Liaison Officer, DEEP, we understand that a phone call between our technical staff and the DEEP would be responsive to your request. As such, we plan to coordinate a call with Mr. Semancik at an appropriate time to update you on our assessment of the continued safe operation of the facility.
Thank you for your interest in this issue. We hope that we have been responsive to your requests. If you would like to discuss this further, please feel free to contact either myself at (610) 337-5299 or Mr. Jonathan Greives, Regional State Liaison Officer at (610) 337-5337.
Sincerely,
(Original Signed by: David C. Lew for)
Daniel H. Dorman Regional Administrator
Enclosure:
Notice of Public Meeting
dated March 9, 2017 (MN 17-003)
cc: Robert Klee, Commissioner, DEEP Jeffrey Semancik, State Liaison Officer, DEEP
Representative Kevin Ryan, Chairperson, NEAC
ML17076A002 ADAMS Package Accession No.: ML17076A004 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/ORA RI/DRP RI/RA NAME JGreives/jeg TSetzer/tcs DDorman/DCL for DATE 3/15/17 3/16/17 3/16/17