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| {{#Wiki_filter: 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 | | {{#Wiki_filter: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 |
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| ==Dear Mr. Kaliszewski:== | | ==Dear Mr. Kaliszewski:== |
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| cc: Robert Klee, Commissioner, DEEP Jeffrey Semancik, State Liaison Officer, DEEP Representative Kevin Ryan, Chairperson, NEAC | | cc: Robert Klee, Commissioner, DEEP Jeffrey Semancik, State Liaison Officer, DEEP Representative Kevin Ryan, Chairperson, NEAC |
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| 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 | | 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}} |
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Revision as of 22:13, 18 May 2018
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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
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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 conduct 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