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| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD. KING OF PRUSSIA, PA 19406-2713 August 29, 2016 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Resources 5000 Dominion Blvd. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD. KING OF PRUSSIA, PA 19406-2713 |
| Glen Allen, VA 23060-6711 | | |
| | August 29, 2016 Mr. David A. Heacock President and Chief Nuclear Officer |
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| | Dominion Resources 5000 Dominion Blvd. |
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| | Glen Allen, VA 23060-6711 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| INITIAL OPERATOR LICENSING OPERATING TEST AND WRITTEN EXAMINATION APPROVAL - MILLSTONE POWER STATION, UNIT 2 | | INITIAL OPERATOR LICENSING OPERATING TEST AND WRITTEN EXAMINATION APPROVAL - MILLSTONE POWER STATION, UNIT 2 |
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| ==Dear Mr. Heacock:== | | ==Dear Mr. Heacock:== |
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| The purpose of this letter is to confirm the final arrangements for the upcoming operator licensing examinations at Millstone Power Station, Unit 2. | | The purpose of this letter is to confirm the final arrangements for the upcoming operator licensing examinations at Millstone Power Station, Unit 2. |
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| The NRC has approved the subject examinations and hereby authorizes you to administer the written examinations in accordance with NUREG-1021, "Operator Licensing Examinations Standards for Power Reactors," Revision 10, on or about September 13, 2016. The NRC staff will administer the operating tests during the week of September 5, 2016. This examination has undergone extensive review by my staff and representatives responsible for licensed operator training at your facility. Based on this review, I have concluded that the examination meets the guidelines of NUREG-1021 for content, operational, and discrimination validity. By administering this examination, you also agree that it meets NUREG-1021 guidelines, and is appropriate for measuring the qualifications of licensed operator applicants at your facility. If you determine that this examination is not appropriate for licensing operators at your facility, do not administer the examination and contact me at (610) 337-5306. | | The NRC has approved the subject examinations and hereby authorizes you to administer the written examinations in accordance with NUREG-1021, "Operator Licensing Examinations Standards for Power Reactors," Revision 10, on or about September 13, 2016. The NRC staff will administer the operating tests during the week of September 5, 2016. This examination has undergone extensive review by my staff and representatives responsible for licensed operator training at your facility. Based on this review, I have concluded that the examination meets the guidelines of NUREG-1021 for content, operational, and discrimination validity. By administering this examination, you also agree that it meets NUREG-1021 guidelines, and is appropriate for measuring the qualifications of licensed operator applicants at your facility. If you determine that this examination is not appropriate for licensing operators at your facility, do not administer the examination and contact me at (610) 337-5306. |
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| Please contact your Chief Examiner, Brian Fuller, at (610) 337-5077, if you have any questions or identify any errors or changes in the license level Reactor Operator (RO) or Senior Reactor Operator (SRO) or type of examination (partial or complete written examination and/or operating test) specified for each applicant. | | Please contact your Chief Examiner, Brian Fulle r, at (610) 337-5077, if you have any questions or identify any errors or changes in the license le vel Reactor Operator (RO) or Senior Reactor Operator (SRO) or type of examination (partial or complete written examination and/or operating test) specified for each applicant. |
| Sincerely, | | |
| | Sincerely, |
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| | /RA/ Donald E. Jackson, Chief |
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| | Operations Branch |
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| | Division of Reactor Safety Docket No. 50-336 License No. DPR-65 |
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| /RA/ Donald E. Jackson, Chief Operations Branch Division of Reactor Safety Docket No. 50-336 License No. DPR-65 cc: Distribution via ListServ
| | cc: Distribution via ListServ |
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| ML16243A013 SUNSI Review Non-Sensitive Publicly Available OFFICE RI/DRS/OB RI/DRS/OB NAME BFuller DEJackson DATE 8/29/16 8/29/16}} | | ML16243A013 SUNSI Review Non-Sensitive Publicly Available OFFICE RI/DRS/OB RI/DRS/OB NAME BFuller DEJackson DATE 8/29/16 8/29/16}} |
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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] Category:License-Operator
MONTHYEARML24281A1102024-10-0707 October 2024 Requalification Program Inspection ML23334A2452023-11-30030 November 2023 75 Day and 150 Day Submittal Letters ML23334A2422023-11-30030 November 2023 Final QA Related Forms ML23298A1652023-10-26026 October 2023 Requalification Program Inspection ML23065A0682023-02-22022 February 2023 Final QA Related Forms ML23047A4142023-02-16016 February 2023 Operator Licensing Retake Examination Approval ML23040A2562023-02-0909 February 2023 Senior Reactor and Reactor Operator Initial License Examinations ML22336A1112022-12-0202 December 2022 U2 - Proposed Operating Test ML22336A1362022-12-0202 December 2022 U2 - NRC Comments on Proposed Licensee-Developed Operating Test ML22336A0932022-12-0202 December 2022 U2 - Proposed Written Examination ML22336A0792022-12-0202 December 2022 U2 - Final Qa/Related Forms ML22336A1262022-12-0202 December 2022 U2 - NRC Comments on Proposed Licensee-Developed Written Exam ML22313A0352022-11-0909 November 2022 U2 - Post Exam Comments and Technical References ML22312A5222022-11-0808 November 2022 U2 - Administered Written Examination with Answer Key ML22312A5292022-11-0808 November 2022 U2 - Administered Operating Test ML22277A2522022-10-0404 October 2022 Requalification Program Inspection ML23003A7862022-09-30030 September 2022 U2 - Proposed Written Examination and Operating Test Outlines (Folder 2) ML23003A7672022-09-30030 September 2022 U2 - Handouts to Applicants (Folder 3) ML23003A7792022-09-30030 September 2022 U2 - Administered Written Examination and Operating Test Outlines (Folder 3) ML23003A7692022-09-21021 September 2022 U2 - Miscellaneous Exam Material (Folder 3) ML22125A1762022-05-0505 May 2022 Preparation and Scheduling of Operator Licensing. ML22083A1892022-03-24024 March 2022 NRC Comments on Draft Licensee-Developed Operating Test (Folder 2) ML22083A1812022-03-24024 March 2022 Final Qa/Related Forms (Folder 1) ML22083A2032022-03-24024 March 2022 Draft Operating Test (Section C) (Folder 2) ML22059B0452022-01-21021 January 2022 Final Operating Test (Section C Only) ML21350A1582021-12-16016 December 2021 Senior Reactor and Reactor Operator Initial License Examinations ML21293A2432021-09-21021 September 2021 Draft Operating Test (Section a, Section B, Section C) (Folder 2) ML21293A2712021-09-21021 September 2021 Post Exam Comments Resolution and References (Folder 1) ML21293A2302021-09-21021 September 2021 Draft Written Examination (Folder 2) ML21293A2202021-09-21021 September 2021 NRC Comments on Draft Licensee-Developed Operating Test (Folder 2) ML21293A2272021-09-21021 September 2021 Draft Written Examination and Operating Test Outlines (Folder 2) ML21293A2502021-09-21021 September 2021 Handouts to Applicants (Folder 3) ML21293A2472021-09-21021 September 2021 Final Written Examination and Operating Test Outlines (Folder 3) ML21263A1442021-09-21021 September 2021 Final Written Examination with Answer Key (401-5 Format) (Folder 3) ML21263A1472021-09-21021 September 2021 Final Operating Test (Sections a, B, and C) (Folder 3) ML21293A1412021-09-21021 September 2021 Miscellaneous Exam Material (Folder 1) ML21293A2182021-09-21021 September 2021 NRC Comments on Draft Licensee-Developed Written Exam (Folder 2) ML21293A1142021-09-21021 September 2021 Final QA Related Forms (Folder 1) 2024-10-07
[Table view] Category:Other HQ and Regional Correspondence
MONTHYEARML21350A1582021-12-16016 December 2021 Senior Reactor and Reactor Operator Initial License Examinations ML19064B3922019-03-0505 March 2019 Senior Reactor and Reactor Operator Initial License Examinations ML16243A0132016-08-29029 August 2016 Initial Operator Licensing Operating Test and Written Examination Approval - Millstone Power Station, Unit 2 ML14262A2522014-09-17017 September 2014 Initial Operator Licensing Operating Test Approval (Millstone Power Station, Unit 2) ML0700901742006-12-28028 December 2006 NRC Region 1 Annual GFE Notification Letter to Multiple Addressees Dtd 12/28/06 ML0527900362005-10-0404 October 2005 Letters to Training Managers of the Region I Facilities Participating in the September 7, 2005 Generic Fundamentals Exam 2021-12-16
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD. KING OF PRUSSIA, PA 19406-2713
August 29, 2016 Mr. David A. Heacock President and Chief Nuclear Officer
Dominion Resources 5000 Dominion Blvd.
Glen Allen, VA 23060-6711
SUBJECT:
INITIAL OPERATOR LICENSING OPERATING TEST AND WRITTEN EXAMINATION APPROVAL - MILLSTONE POWER STATION, UNIT 2
Dear Mr. Heacock:
The purpose of this letter is to confirm the final arrangements for the upcoming operator licensing examinations at Millstone Power Station, Unit 2.
The U.S. Nuclear Regulatory Commission (NRC) has completed its review of the operator license applications submitted in connection with this examination and separately provided a list of approved applicants to Jeffrey T. Stafford, Training Manager. Note that any examination waivers and application denials have been addressed in separate correspondence.
The NRC has approved the subject examinations and hereby authorizes you to administer the written examinations in accordance with NUREG-1021, "Operator Licensing Examinations Standards for Power Reactors," Revision 10, on or about September 13, 2016. The NRC staff will administer the operating tests during the week of September 5, 2016. This examination has undergone extensive review by my staff and representatives responsible for licensed operator training at your facility. Based on this review, I have concluded that the examination meets the guidelines of NUREG-1021 for content, operational, and discrimination validity. By administering this examination, you also agree that it meets NUREG-1021 guidelines, and is appropriate for measuring the qualifications of licensed operator applicants at your facility. If you determine that this examination is not appropriate for licensing operators at your facility, do not administer the examination and contact me at (610) 337-5306.
Please contact your Chief Examiner, Brian Fulle r, at (610) 337-5077, if you have any questions or identify any errors or changes in the license le vel Reactor Operator (RO) or Senior Reactor Operator (SRO) or type of examination (partial or complete written examination and/or operating test) specified for each applicant.
Sincerely,
/RA/ Donald E. Jackson, Chief
Operations Branch
Division of Reactor Safety Docket No. 50-336 License No. DPR-65
cc: Distribution via ListServ
ML16243A013 SUNSI Review Non-Sensitive Publicly Available OFFICE RI/DRS/OB RI/DRS/OB NAME BFuller DEJackson DATE 8/29/16 8/29/16