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Category:Letter
MONTHYEARML24240A1692024-09-18018 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) 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 ML24162A0882024-06-10010 June 2024 Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications 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) 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 ML24141A1502024-05-20020 May 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications 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 ML24123A2272024-05-0202 May 2024 Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24123A2042024-05-0202 May 2024 Pre-Decisional Replay to EA-23-144 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 ML24093A1022024-04-0101 April 2024 Alternative Request IR-4-13, Proposed Alternative Request to Support Steam Genera Tor Channel Head Drain Modification 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 IR 05000336/20240112024-04-0101 April 2024 Comprehensive Engineering Team Inspection - Inspection Report 05000336/2024011 and 05000423/2024011 ML24092A0752024-03-28028 March 2024 3R22 Refueling Outage Inservice Inspection (ISI) Owners Activity Report Extension ML24088A2352024-03-26026 March 2024 Decommissioning Funding Status Report ML24086A4762024-03-22022 March 2024 Application for Technical Specification Change to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line-Item Improvement Process ML24086A4802024-03-22022 March 2024 Alternative Request IR-4-14, Proposed Alternative Request to Defer ASME Code Section XI Inservice Inspection Examination for Pressurizer and Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles ML24051A1922024-03-0808 March 2024 – Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000336/20230062024-02-28028 February 2024 Annual Assessment Letter for Millstone Power Station, Units 2 and 3, (Reports 05000336/2023006 and 05000423/2023006) ML24053A2632024-02-21021 February 2024 Unit 3, and Independent Spent Fuel Storage Installation, Notification Pursuant to 10 CFR 72.212(b)(1) Prior to First Storage of Spent Fuel Under a General License ML24057A0612024-02-19019 February 2024 and Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage 2024-09-04
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rffi UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 21OO RENAISSANCE BOULEVARD, SUITE 1OO KING OF PRUSSIA, PENNSYLVANIA 1940$2713 July 17, 2012 Ms. LoriArmstrong Nuclear Training Manager Dominion Nuclear Connecticut, lnc.
Millstone Power Station P. O. Box 128 Waterford. CT 06385
SUBJECT:
JUNE 6,2012, NRC GENERIC FUNDAMENTALS EXAMINATION RESULTS FOR MTLLSTONE POWER STATION, UNlr 3 (COVER LETTER PUBLICLY AVAILABLE, ENCLOSURES WITHHELD FROM PUBLIC)
Dear Ms. Armstrong:
On June 6,2012, the NRC administered the generic fundamentals examination (GFE) section of the written operator licensing examination to employees of your facility. Six of six applicants passed the examination. Enclosed with this letter are copies of the final answer key, the grading results for your facility, and copies of individual examination answer sheets for each of your employees and NRC comments, if any. Please forward the results to the individuals along with the copies of their respective answer sheets. A uP' in the column labeled RESULTS indicates that the individual achieved a passing grade of 80 percent or better on the GFE.
Those individuals having an "F" in the RESULTS column failed the examination.
Approximately 60 days following the examination administration date, a copy of the GFE and the answer key are available for your review at: http://www.nrc.qov/reactors/operator-licensino/qeneric-fundamentals-examinations/past-exams. html lf you have any questions concerning the examination, please contact me at 610-337-5306.
Donald E. Jac Operations Branch Division of Reactor Safety Docket No. 50-423 Enclosures (Non-Public):
- 1. June 2012, NRC Generic Fundamentals Examination Roster Report on Total and Grade for Millstone Power Station. Unit 3
- 2. Individual NRC Examination Answer Sheets cc w/o enclosures: Distribution via ListServ
Ms. LoriArmstrong Nuclear Training Manager Dominion Nuclear Connecticut, lnc.
Millstone Power Station P. O. Box 128 Waterford, CT 06385
SUBJECT:
JUNE 6,2012, NRC GENERIC FUNDAMENTALS EXAMINATION RESULTS FOR MILLSTONE POWER STATION, UNIT 3 (COVER LETTER PUBLICLY AVAILABLE, ENCLOSURES WITHHELD FROM PUBLIC)
Dear Ms. Armstrong:
On June 6,2012, the NRC administered the generic fundamentals examination (GFE) section of the written operator licensing examination to employees of your facility. Six of six applicants passed the examination. Enclosed with this letter are copies of the final answer key, the grading results for your facility, and copies of individual examination answer sheets for each of your employees and NRC comments, if any. Please fonvard the results to the individuals along with the copies of their respective answer sheets. A "P" in the column labeled RESULTS indicates that the individual achieved a passing grade of 80 percent or better on the GFE.
Those individuals having an "F" in the RESULTS column failed the examination.
Approximately 60 days following the examination administration date, a copy of the GFE and the answer key are available for your review at: http://www.nrc.qov/reactorsloperator-licensino/qeneric-fundamentals-exam inations/past-exams. html lf you have any questions concerning the examination, please contact me at 610-337-5306.
Sincerely,
/RN Donald E. Jackson, Chief Operations Branch Division of Reactor Safety Docket No. 50-423 Enclosures (Non-Public):
- 1. June 2012, NRC Generic Fundamentals Examination Roster Report on Total and Grade for Millstone Power Station, Unit 3
- 2. Individual NRC Examination Answer Sheets cc w/o enclosures: Distribution via ListServ DOCUMENT NAME: GiDRS\Operations Branch\GFE\MS36-06-12-GFE Resultsltr.docx A,DAMS PKG NO.: M112178A136 ADAMS ACCESSION NUMBER: M112193A133 g suNstReview V Non-Sensitive V Publicly Available D Sensitive tr Non-Publicly Available OFFICE RI/DRS/OB RI/DRS/OB NAME CBixler DEJackson DATE 07t11t12 07t11112 ICIAL RECORD COPY