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Category:Inspection Report
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 IR 05000336/20244022024-10-0808 October 2024 Security Baseline Inspection Report 05000336/2024402 and 05000423/2024402 (Cover Letter Only) 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 IR 05000336/20244412024-08-0606 August 2024 Supplemental Inspection Report 05000336/2024441 and 05000423/2024441 and Follow-Up Assessment Letter (Cover Letter Only) 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 IR 05000336/20240102024-06-26026 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000336/2024010 and 05000423/2024010 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) 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 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) IR 05000336/20240112024-04-0101 April 2024 Comprehensive Engineering Team Inspection - Inspection Report 05000336/2024011 and 05000423/2024011 IR 05000336/20230062024-02-28028 February 2024 Annual Assessment Letter for Millstone Power Station, Units 2 and 3, (Reports 05000336/2023006 and 05000423/2023006) IR 05000336/20230042024-02-14014 February 2024 Integrated Inspection Report 05000336/2023004 and 05000423/2023004 IR 05000336/20234022024-01-30030 January 2024 Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only) IR 05000336/20234402024-01-11011 January 2024 Special Inspection Report 05000336/2023440 and 05000423/2023440 (Cover Letter Only) IR 05000336/20230032023-11-0606 November 2023 Integrated Inspection Report 05000336/2023003 and 05000423/2023003 IR 05000336/20234202023-10-0404 October 2023 Security Inspection Report 05000336/2023420 and 05000423/2023420 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) IR 05000336/20230022023-08-0909 August 2023 Integrated Inspection Report 05000336/2023002 and 05000423/2023002 IR 05000336/20234012023-07-17017 July 2023 Material Control and Accounting Program Inspection Report 05000336/2023401 and 05000423/2023401 - (Cover Letter Only) IR 07200047/20234012023-06-0808 June 2023 NRC Independent Spent Fuel Storage Installation Security Inspection Report No. 07200047/2023401 IR 05000336/20230012023-05-0808 May 2023 Integrated Inspection Report 05000336/2023001 and 05000423/2023001 IR 05000336/20234032023-05-0202 May 2023 Public - Millstone Power Station, Units 2 and 3 – Final Significance Determination of Green Finding; Inspection Report 05000336/2023403 and 05000423/2023403 IR 05000336/20233022023-03-0707 March 2023 Operator Licensing Retake Examination Report 05000336/2023302 IR 05000336/20220062023-03-0101 March 2023 Annual Assessment Letter for Millstone Power Station, Units 2 and 3 (Reports 05000336/2022006 and 05000423/2022006) IR 05000336/20220042023-02-13013 February 2023 Integrated Inspection Report 05000336/2022004 and 05000423/2022004 IR 05000336/20224012023-01-26026 January 2023 Security Baseline Inspection Report 05000336/2022401 and 05000423/2022401 and Preliminary Finding(S) of Greater than Very Low Significance and Apparent Violation(S) (Cover Letter Only) IR 05000245/20220012023-01-0909 January 2023 – Safstor Inspection Report 05000245/2022001 IR 05000336/20224032023-01-0505 January 2023 Cyber Security Inspection Report 05000336/2022403 and 05000423/2022403 IR 05000336/20225012022-12-14014 December 2022 Reissued Emergency Preparedness Biennial Exercise Inspection Report 05000336/2022501 and 05000423/2022501 IR 05000336/20223012022-11-22022 November 2022 Initial Operator Licensing Examination Report 05000336/2022301 ML22325A1042022-11-21021 November 2022 Emergency Preparedness Biennial Exercise Inspection Report 05000336/2022501 and 05000423/2022501 IR 05000336/20220032022-11-14014 November 2022 Integrated Inspection Report 05000336/2022003 and 05000423/2022003 IR 05000336/20220102022-11-0101 November 2022 Biennial Problem Identification and Resolution Inspection Report 05000336/2022010 and 05000423/2022010 IR 05000336/20220112022-09-0808 September 2022 Triennial Fire Protection Inspection Report 05000336/2022011 and 05000423/2022011 IR 05000336/20220052022-08-31031 August 2022 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Report 05000336/2022005 and 05000423/2022005) IR 05000336/20220022022-08-11011 August 2022 Integrated Inspection Report 05000336/2022002 and 05000423/2022002 IR 05000336/20224022022-05-23023 May 2022 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000336/2022402 and 05000423/2022402 IR 05000336/20220012022-05-10010 May 2022 Integrated Inspection Report 05000336/2022001 and 05000423/2022001 IR 05000423/20223022022-03-0707 March 2022 Operator Licensing Retake Examination Report 05000423/2022302 IR 05000336/20210062022-03-0202 March 2022 Annual Assessment Letter for Millstone Power Station, Units 2 and 3 (Reports 05000336/2021006 and 05000423/2021006) IR 05000336/20210042022-02-10010 February 2022 Integrated Inspection Report 05000336/2021004 and 05000423/2021004 IR 05000336/20210112022-01-20020 January 2022 Post-Approval Site Inspection for License Renewal - Phase 4 Inspection Report 05000336/2021011 IR 05000336/20210032021-11-12012 November 2021 Integrated Inspection Report 05000336/2021003 and 05000423/2021003 IR 05000423/20213012021-11-10010 November 2021 Initial Operator Licensing Examination Report 05000423/2021301 2024-08-06
[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
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May 2, 2007Mr. David A. ChristianSr. Vice President and Chief Nuclear Officer Dominion Resources 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE UNIT 3 OPERATOR AND SENIOR REACTOR OPERATORINITIAL EXAMINATION REPORT NO. 05000423/2007301
Dear Mr. Christian:
This report transmits the results of the Reactor Operator (RO) and Senior Reactor Operator(SRO) licensing examination conducted by the NRC during the period of March 12 -19, 2007.
This examination addressed areas important to public health and safety and was developed and administered using the guidelines of the "Examination Standards for Power Reactors" (NUREG-1021, Revision 9).Based on the results of the examination, all ten applicants passed all portions of theexamination. The ten applicants included five ROs, one instant SRO and four upgrade SROs.
Examination results indicated that the applicants were well prepared for the examination.
Mr. D. Silk discussed performance insights observed during the examination with Mr. T. Horner on March 16, 2007. On April 5, 2007, final examination results, including individual license numbers, were given during a telephone call between Mr. M. Sykes and Mr. T. Horner.In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and itsenclosure will be available electronically for public inspection in the NRC Public DocumentRoom or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). These records include the final examination and are available in ADAMS (Master File - Accession Number ML060800095; RO and SRO Written - Accession Number ML070990457; RO and SRO Operating Section A - Accession Number ML070990466; RO and SRO Operating Section B - Accession Number ML070990481; and RO and SRO Operating Section C - Accession Number ML070990501). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Mr. D. Christian2Should you have any questions regarding this examination, please contact me at (610) 337-5046, or by E-mail at MD S1@NRC.GOV.Sincerely,/RA/Marvin D. Sykes, ChiefOperations Branch Division of Reactor SafetyDocket No: 50-423License No: NPF-4
Enclosure:
Initial Examination Report No. 05000423/2007301 cc w/encl:J. A. Price, Site Vice President, Millstone StationC. L. Funderburk, Director, Nuclear Licensing and Operations Support D. W. Dodson, Supervisor, Station Licensing L. M. Cuoco, Senior Counsel C. Brinkman, Manager, Washington Nuclear Operations J. Roy, Director of Operations, Massachusetts Municipal Wholesale Electric Company First Selectmen, Town of Waterford B. Sheehan, Co-Chair, NEAC E. Woollacott, Co-Chair, NEAC E. Wilds, Director, State of Connecticut SLO Designee J. Buckingham, Department of Public Utility Control G. Proios, Suffolk County Planning Dept.
R. Shadis, New England Coalition Staff G. Winslow, Citizens Regulatory Commission (CRC)
S. Comley, We The People D. Katz, Citizens Awareness Network (CAN)
R. Bassilakis, CAN J. M. Block, Attorney, CAN P. Eddy, Electric Division, Department of Public Service, State of New York P. Smith, President, New York State Energy Research and Development Authority J. Spath, SLO Designee, New York State Energy Research and Development Authority J. T. Spence, Manager - Nuclear Training Mr. D. Christian2Should you have any questions regarding this examination, please contact me at (610) 337-5046, or by E-mail at MDS1@NRC.GOV.Sincerely,/RA/Marvin D. Sykes, ChiefOperations Branch Division of Reactor SafetyDocket No: 50-423License No: NPF-49
Enclosure:
Initial Examination Report No. 05000423/2007301 cc w/encl:J. A. Price, Site Vice President, Millstone StationC. L. Funderburk, Director, Nuclear Licensing and Operations SupportD. W. Dodson, Supervisor, Station Licensing L. M. Cuoco, Senior Counsel C. Brinkman, Manager, Washington Nuclear Operations J. Roy, Director of Operations, Massachusetts Municipal Wholesale Electric CompanyFirst Selectmen, Town of Waterford B. Sheehan, Co-Chair, NEAC E. Woollacott, Co-Chair, NEAC E. Wilds, Director, State of Connecticut SLO Designee J. Buckingham, Department of Public Utility Control G. Proios, Suffolk County Planning Dept.
R. Shadis, New England Coalition Staff G. Winslow, Citizens Regulatory Commission (CRC)
S. Comley, We The People D. Katz, Citizens Awareness Network (CAN)
R. Bassilakis, CAN J. M. Block, Attorney, CAN P. Eddy, Electric Division, Department of Public Service, State of New YorkP. Smith, President, New York State Energy Research and Development Authority J. Spath, SLO Designee, New York State Energy Research and Development AuthorityJ. T. Spence, Manager - Nuclear TrainingSUNSI Review Complete: DMS (Reviewer's Initials
)ADAMS PKG: ML060800095ADAMS: ML071220278DOCUMENT NAME: G:\DRS\Operations Branch\SILK\Exam FY07-MS3 Mar 07 (U01638)\ExamReport.wpd After declaring this document "An Official Agency Record" it will be released to the Public.To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy withattachment/enclosure "N" = No copyOFFICERI/DRS/OBRI/DRS/OBRI/DRS/OBNAMECJBixler/DMS forDMSilk/DMSMDSykes/MDSDATE05/1/0705/1/0705/2/07OFFICIAL RECORD COPY Mr. D. Christian3Distribution w/encl
- DRS Master Exam File (C. Bixler) (w/concurrences)
DRS FileDistribution w/encl
- VIA E-MAIL
- S. Collins, RA M. Dapas, DRA A. R. Blough, DRS M. Sykes, DRS D. Silk, Chief Examiner, DRS J. Lamb, RI OEDO H. Chernoff, NRR J. Lubinski, NRR V. Nerses, NRR, PM E. Miller, NRR S. Schneider, Senior Resident Inspector E. Bartels, Resident OA R. Powell, DRP P. Krohn, DRP B. Norris, DRP Region I Docket Room (with concurrences)S. Glenn, INPO (GlennSG@Inpo.org)
iEnclosureU. S. NUCLEAR REGULATORY COMMISSIONREGION IDocket No:50-423 License No:NPF-49 Report No:05000423/2007301 Licensee:Dominion Nuclear Connecticut, Inc.
Facility:Millstone Unit 3 Dates:March 19, 2007 (Written Examination Administration)March 12-16, 2007 (Operating Test Administration)
March 27, 2007 (Examination Grading)
March 27, 2007 (Final facility post exam comments)Examiners:D. Silk, Senior Operations Engineer (Chief Examiner)B. Haagensen, Operations Engineer G. Johnson, Operations EngineerApproved by:Marvin D. Sykes, ChiefOperations Branch Division of Reactor Safety Enclosure ii
SUMMARY
OF FINDINGSIR 050004243/2007-301; 03/12-19/07; Millstone Unit 3; Initial Operator Licensing Examination.Ten of ten applicants passed the examination (five reactor operators, one SRO instant, and four SRO upgrades). The written examinations were administered by the facility and the operating tests wereadministered by three NRC region-based examiners. There were no inspection findings of significance associated with the examinations.A.NRC-Identified FindingsCornerstone: Mitigating Systems NoneB.Licensee-Identified Findings None EnclosureREPORT DETAILS1.REACTOR SAFETYMitigating Systems - Reactor Operator (RO) and Senior Reactor Operator (SRO) InitialOR Retake License Examination a.Scope of ReviewThe NRC examination team developed the written and operating initial examination andtogether with Millstone Unit 3 training and operations personnel verified or ensured, as applicable, the following: *The examination was prepared and developed in accordance with the guidelinesof Revision 9 of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors." A review was conducted both in the Region I office and at the Millstone plant and training facility. Final resolution of comments and incorporation of test revisions were conducted during and following the onsite preparation week.*Simulation facility operation was proper.
- A test item analysis was completed on the written examination for feedback intothe systems approach to training program.*Examination security requirements were met.
The NRC examiners administered the operating portion of the examination to allapplicants from March 12 to16, 2007. The written examination was administered by the Millstone training staff on March19, 2007. b.FindingsGrading and ResultsAll ten applicants (five ROs and five SROs) passed all portions of the initial licensingexamination.See attachment for a summary of facility post-examination comments.
Examination Administration and PerformanceOne simulator fidelity issue was identified and is detailed in the enclosed SimulationFacility Report.
2Enclosure4OA6Exit Meeting SummaryOn April 5, 2007 the NRC provided conclusions and examination results to Millstone Unit3 management representatives via telephone. License numbers for the ten applicants were also provided during this time. The NRC expressed appreciation for the cooperation and assistance that was providedduring the preparation and administration of the examination by the licensee's training staff.
A1-1AttachmentATTACHMENTSUPPLEMENTAL INFORMATIONKEY POINTS OF CONTACTLicensee PersonnelT. Horner, Supervisor Initial Operator TrainingR. Martin, Unit 3 Shift Supervisor D. Minnich, Unit 3 Instructor R. Royce, Unit 3 Instructor NRCD. Silk, Senior Operations EngineerB. Haagensen, Operations Engineer G. Johnson, Operations EngineerLIST OF ITEMS OPENED, CLOSED, AND DISCUSSEDITEM NUMBERTYPEDESCRIPTIONNONE A2-1AttachmentPost Exam CommentsQuestion No.Facility Comment 65Recommends deleting this question from the examination as there wasno correct answer provided among the four choices. Site specific technical references support this conclusion. The intended answer was developed based upon generic guidance not site specific references.NRC Resolution Comment accepted. Question #65 will be deleted from the examinationbecause no technically correct answer was provided among the choices.
A3-1AttachmentES 501 Simulation Facility ReportFacility Licensee:Millstone Unit 3Facility Docket No:50-423/2007301Operating Tests Administered on: March 12-16, 2007This form is to be used only to report observations. These observations do not constitute auditor inspection findings and, without further verification and review, are not indicative of noncompliance with 10 CFR 55.45(b). These observations do not affect NRC certification or approval of the simulation facility other than to provide information that may be used in future evaluations. No licensee action is required in response to these observations.While conducting the simulator portion of the operating test, the examiners observed thefollowing item:*During the simulator scenario portion of the examination, the reactor tripped and SISactuated due to a small break LOCA. When containment pressure had increased to about 23 psia, the RCS break size was increased to a large break. Containment pressure unexpectedly rose to 60 psia. This caused the simulator to hit an operating limit and freeze. This scenario was run four times and the simulator froze only during the first of four runs with this scenario. During the other runs, containment pressure increased to the expected value of about 45 psia. This issue was documented by the licensee in DR 2007-3.NUREG-1021 Revision 9