IR 05000456/1998304
| ML20217P093 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 04/29/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20217P080 | List: |
| References | |
| 50-456-98-304OL, 50-457-98-304OL, NUDOCS 9805060068 | |
| Download: ML20217P093 (6) | |
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U. S. NUCLEAR REGULATORY COMMISSION REGIONlli Docket Nos:
50-456; 50-457 License Nos:
50-456/98304(OL); 50-457/98304(OL)
Licensee:
Commonwealth Edison Company (Comed)
Facility:
Braidwood Nuclear Power Station, Units 1 and 2 Location:
RR# 1, Box 79 Braceville, IL 60407 Dates:
April 14-15,1998 Examiner:
D. R. McNeil, Chief Examiner Approved by:
Melvyn N. Leach, Chief, Operator Licensing Branch Division of Reactor Safety 9805060068 900429
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PDR ADOCK 05000456 V
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EXECUTIVE SUMMARY
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Braidwood Nuclear Power Station NRC Examination Reports 50-456/98304; 50-457/98304 A Braidwood Station training department developed initial operator licensing retake examination l
was administered to one license applicant.
Results:
i The applicant passed the retake examination and was issued a Senior Reactor Operator's license.
l Examination Summarv:
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The provided JPMs and followup questions met all guidelines of NUREG 1021. The l
applicant appeared well prepared for the test. (Section 05.2)
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Reoort Details
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1. Operations
Operator Training and Qualification 05.1 General Comments
An operator initial license retake examination was administered at the Braidwood j
Nuclear Power Station (BNPS) to one applicant on April 14 - 15,1998. The applicant had failed the Job Performance Measures (JPMs) portion of the October 1997, initial license examination. The applicant passed the retake examination and was issued a Senior Reactor Operator license.
05.2 Ooerating Job Performance Measures a.
Examination Scoce l
The BNPS training department developed the retake operating test. The test consisted
of ten JPMs, each of which had two follow-up questions.
b.
Observations and Findings The BNPS training staff selected a wide variety of JPMs that examined the applicant in all safety functional groups outlined in NUREG 1021, " Operator Licensing Examination Standards for Power Reactors," Interim Revision 8, January 1997.
The majority of the JPM follow up questions were open reference questions. The questions were written to the right difficulty level and were not direct lookup questions.
The designation of open or closed reference to the followup questions was correct in
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each case.
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The simulator was accurately set up at the beginning of the JPMs such that there were I
no problems with the administration of the JPMs.
The applicant was able to complete all of the JPMs and their followup questions with no errors.
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Conclusions The provided JPMs and followup questions met all guidelines of NUREG 1021. The applicant appeared well prepared for the test.
05.3 Simulator Fidelity i
The examiner observed no simulator modeling deficiencies during the examination administration.
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V. Management Meetings
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X1 Exit Meeting Summarv
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The chief examiner presented the examiner's observations and findings to members of the i
licensee's management on April 15,1998. The licensee acknov iedged the findings presented.
No proprietary information was identified during the examination or at the exit meeting.
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PARTIAL LIST OF PERSONS CONTACTED
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Licensee P. Artusa, Operations Dept. Training Coordinator T. Benton, ILT Group Lead E. Hendrix, Operations Staff Supervisor P. Hippely, NGG Operations Exam Coordinator M. Prospero, Shift Manager J. Walker, Training Manager NBC C. Phillips, Senior Resident inspector J. Adams, Resident inspector ITEMS OPENED, CLOSED, AND DISCUSSED Ooened None Closed None Discussed None
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Enclosure 2 SIMULATION FACILITY REPORT Facility Licensee: Braidwood Nuclear Power Station Facility Licensee Docket No: 50-456;50-457 Operating Tests Administered: April 14-15,1998 The following documents observations made by the NRC examination team during the April 1998, initial retake license examination. These observations do not constitute audit or inspection findings and are not, without further verification and review, indicative of non-comp!iance with 10 CFR 55.45(b). These observations do not affect NRC certification or approval of the simulation facility other than to provide information which may be used in future evaluations. No licensee action is required in response to these observations.
During the conduct of the simulator portion of the operating tests, the following items were observed:
ITEM DESCRIPTION none
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