IR 05000445/1999301

Exam Repts 50-445/99-301 & 50-446/99-301 on 990618-24.Exam Results:Six Applicants for Senior Operator Licenses Passed Exams

ML20210C345
Person / Time
Site:	Comanche Peak
Issue date:	07/16/1999
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20210C338	List: IR 05000445/1999301 ML20210C333
References
50-445-99-301, 50-446-99-301, NUDOCS 9907260035
Download: ML20210C345 (6)

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ENCLOSURE U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

Docket Nos.: 50-445;50-446 License Nos.: NPF-87; NPF-89

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. Report No : 50-445/99-301;50'-446/99-301 Licensee: TU Electric Facility: Comanche Peak Steam Electric Station, Units 1 and 2 Location: FM-56 Glen Rose, Texas Dates: June 18 to 24,1999 Inspectors: Howard F. Bundy, Senior Reactor Engineer i Gary W. Johnston, Senior Reactor Engineer Thomas Meadows, Senior Reactor Engineer (Chief Examiner)

Approved By: John L. Pellet,' Chief, Operations Branch Division of Reactor Safety l l

' ATTACHMENTS:

Attachment 1: Supplemental information Attachment 2: Facility initial Examination Comments Attachment 3: Final Written Examinations and Answer Keys i

9907260035 990716 PDR l V ADOCK 05000445

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EXECUTIVE SUMMARY

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Comanche Peak Steam Electric Station, Units 1 and 2 NRC Inspection Report No. 50-445/99-301; 50-446/99-301 ]

i NRC examiners evaluated the competency of six senior operator applicants for issuance of

operating licenses at the Comanche Peak Steam Electric Station, Units 1 and 2. The NRC l

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developed the initial licerise examinations using the guidance in NUREG-1021, Revision 8, April 1999. The initial written examinations were administered to six applicants on June 18,1999, by NRC and facility proctors in accordance with the guidance in NUREG-1021, Revision 8. The NRC examiners administered the operating tests June 21-24,199 Ooerations .

. The six applicants for tanior operator licenses passed their examinations. Overall, j applicants demonstrated effective oversight and adequate communication techniques 4 during the dynamic scenarios, with normally effective peer and self checking

'(Sections O4.1 and 04.2).

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l-3-Report Details

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Summary of Plant Status Both units operated at 100 percent power for the duration of this inspectio I. Operations 04 _ Operator Knowledge and Performance

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0 initial Written Examination Insoection Scooe On June 18,1999, the NRC and the facility licensee proctored the administration of the written examination, approved by the chief examiner and NRC Region IV supervision, to six individuals who had applied for a senior reactor operator license. The NRC graded the written examinations and evaluated the results for question validity and generic weaknesse Observations and Findinas The applicants passed the written examination. Written examination scores ranged from a low of 90 to a high of 100 percent with an average of 96 percent. Post-examination review indicated that the questions missed were primarily due to isolated knowledge and training weaknesses. No broad generic training weaknesses were identified as a result of the missed question analysis. The licensee's post-examination review resulted in no comment ! Conclusions The license applicants passed the written examinations. No broad knowledge or

-- training weaknesses were identified as a result of evaluation of the graded )

examination O4.2 Initial Operatina Test ' Inspection Scope

. The examination team adminir,tered the various parts of the operating examination to

' the six applicants on June 21-24,1999. Each applicant participated in three scenario Each applicant was formally evaluated for a senior operator license. Each of the three upgrade applicants received a control room and facilities walkthrough test, which consisted of five tasks, and an administrative test, which consisted of five tasks in four administrative areas. The three instant applicants recieved an identical examination with five additional tasks that also tested reactor operator skills, t

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' b. - . Observations ano Findinas .

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The applicants pessed all' sections of the operating test. The examiners noted E '

' appropriate use of peer and self-checking practices in all areas of the examination 'One applicant did not perform self-checking at a high level during the integrated plant

- section of th'e operating test, but peer checking and three way.commupications

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prevented significant impact; When evaluated in the senior operator in charge position

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.for the dynamic scenarios, the examiners observed that all applicants demonstrated .

- effective oversight and adequate communication techniques. The applicants directed crew actions, such that, the priority for mitigating actions was effective and efficient.

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i Communication was usually three way and effective. The applicants displayed correct application of technical specifications and emergency and abnormal procedures that -

justified their action The' applicants ' generally performed well on the systems and facility walkthrough and administrative tasks. All critical tasks were performed such that the tasks were

! . completed correct! Conclusions The six applicants for senior operator licenses passed their examinations. Overall,.

applicants demonstrated effective oversight and adequate communication techniques

'during the dynamic scenarios, with normally effective peer and self checking, 05- Operator Training and Qualification f

05.1 : Initial Licensina Examination Develooment . Inspection Scope

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The NRC developed the initial licensing examination in accordance with NUREG-1021,

" Operator Licensing Examination Standards for Power Reactors," Revision ' b; Observations and Finuinas The NRC developed the initial licensing examination in accordance with ' guidance provided in'NUREG-1021. The facility provided some of the reference materials in electronic media which was easily used for examination development. The material iprovided adequately supported development of all sections of the examinatio ,

. Conclusions C The facility provided reference material that adequately supported development of all sections of the examinatio ,

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-5-0 Simulator Performance No fidelity problems were identified with the simulator. The simulator performed well in that it effectively duplicated real plant response and caused minimal delays in examination administration. The simulator staff provided effective technical and

. logistical support in the examination administratio .3 Examination Security

. Scope The examiners reviewed examination security both during onsite preparation week and examination administration week for compliance with NUREG-1021 requirement Qbservations and Findinas Members of the licensee's operations and trainirig staff signed onto the NUREG-1021 approved examination security agreement acknowledging their responsibilities for examination security. The licensee maintained secure areas for examination development, review, validation, and administration. Signs were conspicuously posted to avoid inadvertent unauthorized access, and doors were maintained locked with good key control to ensure proper access to sensitive areas.' Applicants were maintained under constant supervision and were always escorted to and from examination point Conclusions Effective examination security was maintained.-

V. Management Meetings X1 Exit Meeting Summary The chief examiner presented the preliminary inspection results to members of the licensee management at the conclusion of the operatir.g test administration on June 24,

.1999. The licensee acknowledged the findings presente

The licensee did not identify as proprietary any information or materials examined during the inspectio l l

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ATTACHMENT 1 SUPPLEMENTAL INFORMATION PARTIAL LIST OF PERSONS CONTACTED Licensee M. Blevins, VP, Nuclear Operations S. Falley, Supervisor, Nuclear Training

- B. Guldemund, Shift Operations Manager D. Moore, Manager, Operations P.' Presley, Senior Training instuctor M. Sunseri, Manager, Nuclear Training NR Paul Gage, Senior Reactor Engineer John Pellet, Chief, Operations Branch Tom Stetka, Senior Reactor Engineer INSPECTION PROCEDURE USED NUREG-1021 " Operator Licensing Examination Standards for Power Reactors,"

Revision 8 ,

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