ML071220278: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(Created page by program invented by StriderTol)
Line 3: Line 3:
| issue date = 05/02/2007
| issue date = 05/02/2007
| title = IR 050004243-07-301; 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)
| title = IR 050004243-07-301; 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)
| author name = Sykes M D
| author name = Sykes M
| author affiliation = NRC/RGN-I/DRS/OB
| author affiliation = NRC/RGN-I/DRS/OB
| addressee name = Christian D A
| addressee name = Christian D
| addressee affiliation = Dominion Resources, Inc
| addressee affiliation = Dominion Resources, Inc
| docket = 05000423
| docket = 05000423

Revision as of 01:13, 13 July 2019

IR 050004243-07-301; 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)
ML071220278
Person / Time
Site: Millstone Dominion icon.png
Issue date: 05/02/2007
From: Marvin Sykes
Operations Branch I
To: Christian D
Dominion Resources
Shared Package
ML060800095 List:
References
IR-07-301
Download: ML071220278 (12)


Text

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