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Category:Letter
MONTHYEARIR 05000336/20240022024-08-13013 August 2024 Integrated Inspection Report 05000336/2024002 and 05000423/2024002 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 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations 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 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) 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) 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 ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report 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 ML24123A1222024-04-30030 April 2024 Inservice Inspection Program - Owners Activity Report, Refueling Outage 22 IR 05000336/20244012024-04-30030 April 2024 Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only) IR 05000336/20244402024-04-25025 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 IR 05000336/20234022024-01-30030 January 2024 Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only) ML24030A7522024-01-30030 January 2024 Technical Specification Bases Pages 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 . ML23361A0312023-12-20020 December 2023 Intent to Pursue Subsequent License Renewal 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) 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. 2024-08-06
[Table view] Category:Licensee Response to Notice of Violation
MONTHYEARML17320A1212017-11-0303 November 2017 Clarification to the Reply to a Notice of Violation, EA-16-090 ML16278A6022016-09-29029 September 2016 Follow-Up to a Reply to a Notice of Violation, EA-16-090 ML16162A1702016-06-0303 June 2016 Reply to Notice of Violation; EA-16-090 ML15097A0842015-03-31031 March 2015 Reply to a Notice of Violation EA-14-126 ML14325A0602014-11-19019 November 2014 Reply to a Notice of Violation; EA-14-092 ML14209A0122014-07-24024 July 2014 Reply to a Notice of Violation ML13350A1372013-12-0909 December 2013 Reply to Notice of Violation 05000423-13-004-01 ML0516602572005-06-0808 June 2005 Response to NRC Inspection Report Nos. 05000336-05-009 and 05000423-05-009 ML0210203282002-03-28028 March 2002 Response to Apparent Violations in Inspection Report No.05000245/2001013 2017-11-03
[Table view] |
Text
'Dominion Nuclear Connecticut, Inc. o 5000 Dominion Boulevard. Glen Allen, VA 23060 D n e Web Address: wwvw.dom.com December 9, 2013 U.S. Nuclear Regulatory Commission Serial No.13-623 Attention: Document Control Desk NSSL/TGC RO Washington, DC 20555-0001 Docket No. 50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3 REPLY TO A NOTICE OF VIOLATION VIO 05000423/2013004-01 Pursuant to the provisions of 10 CFR 2.201, Dominion Nuclear Connecticut, Inc. (DNC) herein provides a reply to NRC letter dated November 8, 2013 regarding the failure to restore compliance within a reasonable time for the Millstone Power Station Unit 3 (MPS3) feedwater isolation valves. provides DNC's response to the violation of NRC requirements specified in the Notice of Violation VIO 05000423/2013004-01. This enclosure provides: (1) the reason for the violation, (2) the corrective steps that have been taken and the results achieved; (3) the corrective steps that will be taken, and (4) the date when full compliance will be achieved.
If you have any questions or require further information, please contact Mr. William D.
Bartron at (860) 444-4301.
Sincerely, Daniel G. Stoddard Senior Vice President - Nuclear Operations
Enclosure:
- 1. Reply to a Notice of Violation VIO 05000423/2013004-01 Commitments made in this letter:
- 1. DNC will complete a modification that will correct the degraded closing capability of the MPS3 main feedwater isolation valves prior to the restart from refueling outage 3R16.
Serial No.13-623 Docket No. 50-423 Page 2 of 2 cc: Regional Administrator U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd.
Suite 100 King of Prussia, PA 19406-2713 J. S. Kim Project Manager - Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08 C2A Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station
Serial No.13-623 Docket No. 50-423 Enclosure 1 REPLY TO A NOTICE OF VIOLATION VIO 05000423/2013004-01 MILLSTONE POWER STATION UNIT 3 DOMINION NUCLEAR CONNECTICUT, INC.
Serial No.13-623 Docket No. 50-423 Enclosure Page 1 of 2 NOTICE OF VIOLATION "During an NRC inspection conducted between July 1 and September 30, 2013 a violation of NRC requirements was identified. In accordance with the NRC Enforcement Policy, the violation is listed below:
10 CFR 50 Appendix B, Criterion XVI, "Corrective Action," requires, in part, that measures shall be established to assure that conditions adverse to quality are promptly identified and corrected.
Contrary to the above, from 2007 until the present, Dominion failed to correct the degraded closing capability of the Unit 3 main feedwater isolation valves and has not restored compliance within a reasonable period of time. Specifically, following Dominion's initial documentation of the issue in 2007, and the subsequent inspectors' documentation of the corrective action violation in inspection report 05000423/2012010, Dominion has since deferred repairsuntil the October2014 outage.
This violation is associatedwith a Green SDP finding."
Response to Notice of Violation
- 1) Reason for the violation, or, if contested, the basis for disputing the violation or severity level Dominion Nuclear Connecticut, Inc. (DNC) concurs with the violation as stated.
The reason for the violation is that DNC did not appropriately plan for a project of the scope and complexity required. Critical tasks to support resolution and due dates for these tasks were not sufficiently developed, defined, and tracked. Key dates were missed due to changes in the scope of work based on more complex corrective actions than originally planned.
In 2007, a discrepancy was identified in the closing calculations associated with 3FWS*CTV41AIB/C/D, Steam Generator Feedwater Isolation Trip Valves. An Operability Determination determined the valves were Operable but Not Fully Qualified.
At that time, it was believed that the issue could be resolved without a physical modification in the plant.
Later, it was determined that a physical modification was required to correct the condition (installation of new valve actuators). The scope and complexity of this project was not fully recognized initially and thus did not receive adequate project management.
Critical tasks including design details, funding, material purchases and deliveries, vendor engineering documentation, and project implementation scheduling were not sufficiently developed, defined, or tracked.
Serial No.13-623 Docket No. 50-423
- 2 Enclosure Page 2 of 2 In 2012, the NRC conducted a Problem Identification & Resolution inspection, and issued Green Non-cited Violation (NCV)05000423/2012010-01 because DNC had not implemented actions to close the open Operability Determination in a timely manner.
To address the NCV, DNC conducted an apparent cause evaluation (ACE), which identified the cause as discussed above. At that time, the project completion was targeted for the spring 2013 refueling outage (3R15).
Subsequent to the approval of the ACE, internal design reviews commenced and an independent design organization was commissioned to review the project. Additional technical concerns with the proposed design were identified, and as a result of these concerns, the project implementation was delayed for an additional fuel cycle to 3R16 (fall 2014).
- 2) Corrective steps that have been taken and the results achieved A design modification was approved on November 5, 2013 that will correct the degraded closing capability of the steam generator feedwater isolation trip valves. As a result, critical tasks to support implementation of the design change have been developed and defined. The newly specified outage milestones for this project have been met to date.
- 3) Corrective steps that will be taken DNC will complete the design modification to correct the degraded closing capability of the MPS3 main feedwater isolation valves according to the project plan. Critical tasks to support implementation of the design change are being tracked.
- 4) Date when full compliance will be achieved Full compliance will be achieved when DNC completes the modification that will correct the degraded closing capability of the MPS3 main feedwater isolation valves prior to the restart from refueling outage 3R16 (fall 2014).