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Category:Inspection Report Correspondence
MONTHYEARIR 05000245/20164032016-09-29029 September 2016 Millstone Power Station, Units 2 and 3 - Security Inspection Report 05000336/2016403 and 05000423/2016403. Letter Only IR 05000336/20164032016-09-29029 September 2016 Security Inspection Report 05000336/2016403 and 05000423/2016403. Letter Only ML0902800902009-01-27027 January 2009 Notification of Inspection and Request for Information ML0820504522008-07-23023 July 2008 Notification of Conduct of a Triennial Fire Protection Baseline Inspection IR 05000336/20052022007-10-0303 October 2007 Letter to Mr. D. Christian - Millstone Power Station, Units 2 and 3 - NRC Material Control and Accounting Program Inspection Report No. 05000336/2005202 and 05000423/2005202 ML0631102852006-11-0606 November 2006 Response to Evaluation of a Non-cited Violation (NRC Integrated Inspection Report Numbers 05000336/2006006 and 05000423/2006006 IR 05000336/20060122006-10-0404 October 2006 IR 05000336-06-012, IR 05000423-06-012, 08/21/2006 - 08/25/2006, Millstone Power Station, Units 2 and 3, Physical Protection IR 05000336/20060152006-08-25025 August 2006 IR 05000336/2006015 and 05000423/2006015; Millstone Power Station, Units 2 and 3; Ti 2515/168 IR 05000336/20050022005-08-10010 August 2005 EA-05-156; Response Letter to Mr. Grecheck (Dominion) from NRC Disputed Violation in Inspection Report 05000336-05-002 and 05000423-05-002 ML0515803152004-10-0404 October 2004 Review of Millstone Unit 2 Steam Generator Tube Inspection Reports for Their 2003 Outage IR 05000336/20040132004-06-0303 June 2004 IR 05000336-04-013, IR 05000423-04-013, on 05/03/2004-05/06/2004; for Millstone Power Station, Physical Security Baseline Inspection Report. Cover Letter ML0412604612004-05-0505 May 2004 Assessment Follow-up Letter-Millstone Power Station, Unit 2 IR 05000336/20020032002-06-13013 June 2002 IR 05000336-02-03; on 03/31-05/11/02; Dominion Nuclear Connecticut, Inc., Millstone Power Station; Unit 2; Resident Inspection. No Violations Identified IR 05000336/20020112002-06-0707 June 2002 IR 05000423-02-011, IR 05000336-02-011, on 04/30-05/03/2002, Dominion Nuclear Connecticut, Inc, Millstone Power Station Units 2 & 3. Emergency Preparedness Exercise & Performance Indicator Review IR 05000336/20020022002-04-24024 April 2002 IR 05000336/2002-002; on 02/10-03/30/02; Dominion Nuclear Connecticut, Inc., Millstone Power Station; Unit 2; Resident Inspection. No Violations Identified IR 05000336/20010152002-03-18018 March 2002 IR 05000336/2001-015 and 05000423/01-015, Millstone Power Station, Inspection on 02/01/02 Related to Biennial Baseline Inspection of Id and Resolution of Problems, Corrective Action Program. Two Violations Were Identified IR 05000336/20010142002-03-0808 March 2002 IR 05000336/2001-014, IR 05000423/2001-014, Dominion Nuclear Connecticut, Inc., Millstone Power Station, Unit 2, Resident Inspection on 12/30/2001-02/09/2002 Re Unit 3, Maintenance Rule Implementation ML0206602472002-03-0707 March 2002 Notification of Conduct of a Triennial Fire Protection Baseline Inspection 2016-09-29
[Table view] Category:Letter
MONTHYEARIR 05000336/20240032024-11-0707 November 2024 Integrated Inspection Report 05000336/2024003 and 05000423/2024003 and Apparent Violation and Independent Spent Fuel Storage Installation Inspection Report 07200008/2024001 ML24289A0152024-10-21021 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) ML24176A1782024-06-20020 June 2024 Update to the Final Safety Analysis Report ML24176A2622024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 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) ML24281A2072024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 (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 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 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 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 ML24093A2162024-04-0101 April 2024 Response to Request for Additional Information Regarding License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits 2024-09-04
[Table view] |
Text
ber 29, 2016
SUBJECT:
MILLSTONE POWER STATION UNITS 2 AND 3 - SECURITY INSPECTION REPORT 05000336/2016403 AND 05000423/2016403
Dear Mr. Stoddard:
On August 26, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed a security inspection at your Millstone Power Station. Th e NRC inspectors discussed the results of this inspection with Mr. John Daugherty, Site Vice President, and other members of your staff.
Inspectors documented the results of this inspection in the enclosed report.
NRC inspectors documented four findings of very low security significance (Green) in this report. These findings involved violations of NRC requirements. Further, NRC inspectors documented a licensee-identified violation which was determined to be of very low security significance. The NRC is treating these violations as non-cited violations (NCV) consistent with Section 2.3.2.a of the Enforcement Policy.
If you contest these violations or the significance, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555 0001; with copies to the Regional Administrator, Region I; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555 0001; and the NRC resident inspector at the
Millstone Power Station.
Three cross-cutting aspects were assigned to the findings in the area of Human Performance; Conservative Bias, because Dominion failed to use decision making-practices that emphasize prudent choices over those that are simply allowable [H.14], Avoid Complacency, because Dominion failed to recognize and plan for the possibility of mistakes and implement appropriate error reduction tools [H.12], and Procedure Adherence, because Dominion failed to follow processes, procedures, and work instructions [H.8]. Additionally, one cross-cutting aspect was assigned to the findings in the area of Problem Identification and Resolution, Resolution, because Dominion failed to take effective corrective actions to address issues in a timely manner [P.3]. If you disagree with the cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region I; and the NRC resident inspector at the Millstone Power Station.
Enclosure contains Sensitive Unclassified Non-Safeguards Information. When separated from enclosure, the transmittal document is decontrolled. In accordance with Title 10 of the Code of Federal Regulations (CFR) 2.390, "Public Inspections, Exemptions, Requests for Withholding,"
of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
However, the material enclosed herewith contains Security-Related Information in accordance with 10 CFR 2.390(d)(1) and its disclosure to unauthorized individuals could present a security vulnerability. Therefore, the material in the enclosure will not be made available electronically for public inspection in the NRC Public Document Room or from the PARS component of NRC's ADAMS.
If you choose to provide a response and Security-Related Information is necessary to provide an acceptable response, please mark your entire response "Security-Related Information-Withhold from public disclosure under 10 CFR 2.390" in accordance with 10 CFR 2.390(d)(1)
and follow the instructions for withholding in 10 CFR 2.390(b)(1). In accordance with
10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response.
Sincerely,
/RA/ Raymond R. McKinley, Chief
Plant Support Branch 1 Division of Reactor Safety Docket Nos. 50-336 and 50-423 License Nos. DPR-65 and NPF-49
Enclosure: Inspection Report 05000336/2016403 and 05000423/2016403 w/Attachment: Supplemental Information
cc w/o encl; w/o OUO-SRI: Distribution via ListServ cc w/encl; w/OUO-SRI: R. Hanson, Security Department Manager J. Semancik, Director, CT Dept of Energy and Environmental Protection