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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) ML24280A0012024-06-20020 June 2024 Update to the Final Safety Analysis Report (Redacted Version) ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24176A2622024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 ML24281A2072024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 (Redacted Version) ML24176A1782024-06-20020 June 2024 Update to the Final Safety Analysis Report ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code 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 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 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 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 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) 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) ML24114A2662024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report ML24116A1742024-04-24024 April 2024 Annual Radiological Environmental Operating 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 2024-09-04
[Table view] Category:License-Operator Examination Report
MONTHYEARIR 05000336/20233022023-03-0707 March 2023 Operator Licensing Retake Examination Report 05000336/2023302 IR 05000336/20223012022-11-22022 November 2022 Initial Operator Licensing Examination Report 05000336/2022301 IR 05000423/20223022022-03-0707 March 2022 Operator Licensing Retake Examination Report 05000423/2022302 IR 05000423/20213012021-11-10010 November 2021 Initial Operator Licensing Examination Report 05000423/2021301 IR 05000336/20203012020-11-12012 November 2020 Initial Operator Licensing Examination Report 05000336/2020301 IR 05000423/20193012019-10-28028 October 2019 Initial Operator Licensing Examination Report 05000423/2019301 IR 05000336/20183012018-11-20020 November 2018 Initial Operator Licensing Examination Report 05000336/2018301 IR 05000423/20173012018-02-0606 February 2018 Initial Operator Licensing Examination Report 05000423/2017301 IR 05000336/20173022017-03-0808 March 2017 Initial Re-take Operator Licensing Examination Report 05000336/2017302 IR 05000336/20163012016-11-23023 November 2016 Initial Operator Licensing Examination Report 05000336/2016301 IR 05000423/20153012015-11-0202 November 2015 Er 05000423/2015301; September 14 to 18, 2015 and September 21, 2015; Millstone Power Station, Unit 3; Initial Operator Licensing Examination Report IR 05000336/20143012015-01-0808 January 2015 Er 05000336/2014301; September 29-October 31, 2014; Millstone Power Station, Unit 2; Initial Operator Licensing Examination Report IR 05000423/20133012014-01-16016 January 2014 Er 05000423/2013301; December 2-9, 2013; Millstone Power Station, Unit 3, Initial Operator Licensing Examination Report IR 05000336/20113012011-12-0606 December 2011 Er 05000336-11-301, on 10/ 3-11/2011, Millstone Power Station, Unit 2, Initial Operator Licensing Examination Report IR 05000423/20113022011-08-0404 August 2011 Er 05000423/11-302, on 7/11-7/18/2011, Millstone Power Station, Unit 3, Initial Operator Licensing Examination Report IR 05000423/20093022009-11-0202 November 2009 Er 05000423-09-302; September 14-22, 2009; Millstone Power Station, Unit 3; Initial Operator Licensing Examination Report IR 05000336/20093012009-05-18018 May 2009 Er 05000336/2009301, January 26 - February 24, 2009, Millstone Power Station, Unit 2, Initial Operator Licensing Examination Report ML0331604982003-11-12012 November 2003 Senior Reactor Operator Initial Examination Report No. 050000336/2003-302 2023-03-07
[Table view] |
Text
UNITED STATES ary 16, 2014
SUBJECT:
MILLSTONE POWER STATION, UNIT 3 - INITIAL OPERATOR LICENSING EXAMINATION REPORT 05000423/2013301
Dear Mr. Heacock:
On December 9, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed an examination at Millstone Power Station, Unit 3. The enclosed report documents the examination findings, which were discussed on December 31, 2013, with Mr. John Stoddard, Millstone Unit 3 Supervisor, Nuclear Shift Operations and other members of your staff.
The examination included the evaluation of four applicants for reactor operator licenses, and three applicants for upgrade senior reactor operator licenses. The written and operating examinations were developed using NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 9, Supplement 1. The license examiners determined that all applicants satisfied the requirements of 10 CFR Part 55, and the appropriate licenses were issued on December 31, 2013.
No findings were identified during this examination.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams/web-based.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Donald E. Jackson, Chief Operations Branch Division of Reactor Safety
Enclosure:
NRC Initial Operator Licensing Examination Report 05000423/2013301 w/Attachments
REGION I==
Docket: 50-423 License: NPF-49 Report : 05000423/2013301 Licensee: Dominion Resources Facility: Millstone Power Station, Unit 3 Location: P. O. Box 128 Waterford, CT 06385 Dates: December 2-5, 2013 (Operating Test Administration)
December 9, 2013 (Written Examination Administration)
December 12, 2013 (Licensee Submitted Post Exam Package)
December 9-30, 2013 (NRC Examination Grading)
December 31, 2013 (Licenses Issued)
Examiners: P. Presby, Chief Examiner, Operations Branch D. Silk, Senior Operations Engineer C. Lally, Operations Engineer J. Tomlinson, Operations Engineer Approved By: Donald E. Jackson, Chief Operations Branch Division of Reactor Safety i
Enclosure
SUMMARY OF FINDINGS
ER 05000423/2013301; December 2-9, 2013; Millstone Power Station, Unit 3, Initial Operator
Licensing Examination Report.
NRC examiners evaluated the competency of four applicants for reactor operator licenses, and three applicants for upgrade senior operator licenses at Millstone, Unit 3. The facility licensee developed the examinations using NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 9, Supplement 1. The written examination was administered by the facility on December 9, 2013. NRC examiners administered the operating tests on December 2-5, 2013. The license examiners determined that all applicants satisfied the requirements of 10 CFR Part 55, and the appropriate licenses have been issued.
NRC-Identified and Self-Revealing Findings
No findings were identified.
Licensee-Identified Violations
None.
ii
REPORT DETAILS
OTHER ACTIVITIES (OA)
4OA5 Other Activities (Initial Operator License Examination)
.1 License Applications
a. Examination Scope
The Chief Examiner reviewed all seven license applications submitted by the licensee to ensure the applications reflected that each applicant satisfied relevant license eligibility requirements. The applications were submitted on NRC Form 398, Personal Qualification Statement, and NRC Form 396, Certification of Medical Examination by Facility Licensee. The examiners also audited one of the license applications in detail to confirm that they accurately reflected the subject applicants qualifications. This audit focused on the applicants experience and on-the-job training, including control manipulations that provided significant reactivity changes.
b. Findings
No findings were identified.
.2 Operator Knowledge and Performance
a. Examination Scope
On December 9, 2013, the licensee proctored the administration of the written examinations to all seven applicants. The licensee staff graded the written examinations, analyzed the results, and presented their analysis to the NRC on December 12, 2013.
The NRC examination team administered the various portions of the operating examination to all seven applicants on December 2-5, 2013. The applicants for reactor operator licenses participated in two dynamic simulator scenarios, in a control room and facilities walkthrough test consisting of eleven system tasks, and an administrative test consisting of four administrative tasks. The applicants for upgrade senior operator licenses participated in one or two dynamic simulator scenarios, a control room and facilities walkthrough test consisting of five system tasks, and an administrative test consisting of five administrative tasks.
b. Findings
All applicants passed all parts of the examination. For the written examinations, the reactor operator applicants average score was 88.33 percent and ranged from 85.33 to 92 percent, the senior operator applicants average score was 90.67 percent and ranged from 88 to 93 percent. The overall written examination average was 89.33 percent. The text of the examination questions and the licensees examination analysis may be accessed in the ADAMS system under the accession numbers noted in
1. In accordance with current NRC policy, the release of this written
examination in ADAMS to the public will be delayed for two years.
Chapter ES-403 and Form ES-403-1 of NUREG 1021 require the licensee to analyze the validity of any written examination questions that were missed by half or more of the applicants. The licensee conducted this performance analysis for four questions that met these criteria and submitted the analysis to the chief examiner. The licensee did not submit any post-examination comments.
.3 Initial Licensing Examination Development
a. Examination Scope
The facility licensee developed the examinations in accordance with NUREG-1021, Revision 9, Supplement 1. All licensee facility training and operations personnel involved in examination preparation and validation were listed on a security agreement.
The facility licensee submitted both the written and operating examination outlines on September 3, 2013. The chief examiner reviewed the outlines against the requirements of NUREG-1021, and provided comments to the licensee. The facility licensee submitted the draft examination package on October 3, 2013. The chief examiner reviewed the draft examination package against the requirements of NUREG-1021, and provided comments to the licensee on the examination on October 29, 2013. The NRC conducted an onsite validation of the operating examinations and provided further comments during the week of November 11, 2013. The licensee satisfactorily completed comment resolution on November 21, 2013.
b. Findings
The examiners determined that the written and operating examinations initially submitted by the licensee were within the range of acceptability expected for a proposed examination.
No findings were identified.
.4 Simulation Facility Performance
a. Examination Scope
The examiners observed simulator performance with regard to plant fidelity during the examination validation and administration. Observations are documented on 2, Simulator Fidelity Report.
b. Findings
No findings were identified.
.5 Examination Security
a. Examination Scope
The examiners reviewed examination security during both the onsite preparation week and examination administration week for compliance with NUREG-1021 requirements.
Plans for simulator security and applicant control were reviewed and discussed with licensee personnel.
b. Findings
No findings were identified.
4OA6 Meetings, including Exit
The Chief Examiner presented the examination results to Mr. John Stoddard, Unit 3 Supervisor, Nuclear Shift Operations, and other members of the licensee's management staff on December 31, 2013. The licensee acknowledged the findings presented.
The licensee did not identify any information or materials used during the examination as proprietary.
ATTACHMENTS:
ATTACHMENT 1 -
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- J. Stoddard, Supervisor, Nuclear Shift Operations
- M. Siebert, Supervisor, Nuclear Training
- P. Scott, Unit 3 Operations
- S. Jackson, Simulator Support - Systems Analyst Specialist
- R. Royce, Nuclear Training Instructor (Exam Developer)
- W. Forrestt, Nuclear Training Instructor (Exam Developer)
NRC Personnel
- J. Ambrosini, Senior Resident Inspector
ITEMS OPENED, CLOSED, AND DISCUSSED
NONE
ADAMS DOCUMENTS REFERENCED