ML20055G392

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Exam Rept 50-341/OL-90-02 on 900528 & 0601-03.Exam Results: Three Reactor Operators & Five Senior Reactor Operators Passed Exams
ML20055G392
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 07/12/1990
From: Hammer J, Jordan M, Morgan M, Riches M
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20055G390 List:
References
50-341-OL-90-02, 50-341-OL-90-2, NUDOCS 9007230125
Download: ML20055G392 (5)


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U..S. NUCLEAR REGULATORY COMMISSION REGION 111 Report'No. 50-341/0L-90-02 Docket No. S0 341- License No. NPF Licensee: The Detroit Edison Company 6400 North Dixie Highway Newport, MI 48166 Facility Name: Fermi 2 Nuclear Plant Examination Administered At: Fermi 2 Nuclear Plant Examination Conducted: May 28 and June 1, 2, and 3, 1990 an Examiner:y.A. Hammer,ChiefExaminer 7-/2-70

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Date Approved By: M. J. Jordan, Chief h /2/70 Licensing Section No. 1 /,

Examination SummarX Examination Administered on May 28. and June 1-3, 1990 (Recort No.

50-341/0L-90-02)

Written and operating examinations were administered to four Reactor Operators (RO) and six Senior Reactor Operators (SRO),

Results: Three R0 and five SR0 candidates passed the examinations.

9007230125 900716 PDR ADOCK 03000341

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REPORT DETAILS

1. Examiners l

- J. Hammer Chief Examiner M. Morgan Examiner, Pacific Northwest Laboratories (PNL)

M. Riches Examiner, ?acific Northwest Laboratories (PNL)

2. Exit Meetino 1

At the conclusion of the site visit the Chief Examiner met with the facility representatives. The following personnel ~ attended this. exit l meeting. l l

Facility Reoresentatives 1

R. McKeon Superintendent of Operatic 1 L.-Goodman Director Nuclear Licensing d G. Reece _ Supervisor Nuclear Training R. Trimai Senior Nuclear Training Specialist NRC Representatives G. Wright Chief OLB, DRS, R III W. Rogers Senior Resident Inspector, Fermi 2 J. Hammer Chief Examiner The following items were discussed during the exit meeting:

a. The candidates were well prepared for the Simulator Operating portion of the examination in the following areas:

o Good procedure usage o Good control board operations o Good-communications between crew members o SR0 leadership skills (command and control)

b. Pre-administration written examination reviews were conducted at the facility during the 14,15, and 16 of May using two of your facility operation staff (one R0 and one SRO). As a result of this review there were few unresolved exam issues.
c. The candidates were not as well prepared for the Administrative portion of the walk through Operating exam as compared to the simulator exams. The candidates with experience prior to employement with Detroit Edison Company were significantly better in the areas of radiation sources, hazards and detector operation and in the interpretation of Pl-thermal limits.

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m--g d.- The examiners - also observed that - sine of the candidates had-

' difficulty in locating equ'pment or panels-outside the control room. -

3.- Duunination Review Attachment 1 has the f acility post exam comments and the Nff's resolution to the comments.

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_he NRC RESOLUTION OF FACILITY COMMENTS y

QUESTION #: R0 74, SR0 82 FACIILITY COMMENT: Change answer from b to c. . Change based on "In addition to taking the mode switch to ' test' (response "b"), the flow unit must be bypassed to clear the rod blocks associated with the failed flow unit."

NRC RESOLUTIbN: Accept facility comment. Master key for R0 and SR0 exams changed, to correct a typographical error.

QUESTION #: R0 13, SR0 13 FACILITY COMMENT: Change answer from b to a. Change based on ST-0P-315--

44-001, table 3: REMOTE SHUTDOWN PANELS PROCESS-INDICATOR DATA, showing that the indicators from response "a" are on the table and the indicators from-response "b" are not.

NRC RESOLUTION: Accept facility comment. Master key for R0 and SR0 exams changes, to correct a typographical error.

QUESTION #: R0 93, SR0 92 FACILITY COMMENT: For part b of both questions, that response "5" is an additional correct answer (Original key stated response "3"). Comment based on student test for Reactor /Recir-culation Flow Control, ST-0P-315-004, and the system operating procedure 23.138.01, as well as the abnormal operating procedures address total system response to various changes in plant conditions. A recirc motor-generator drive motor trip / pump trip will occur when the-discharge valve is 90% open.

-NRC RESOLUTION: Accept facility comment. Haster key for R0 ' and SR0 exams' changed.

QUESTION #: R0 47, SR0 55 FACILITY COMMENT: Answer key states correct response is "b". The facility contends that response "a" is an additional correct response based that . response "a" generates a select error and in accordance with ST-0P315-013-001, ITEM 12, a select error being generated with result in an insert block.

'NRC RESOLUTION: Accept facility comment. Master key for R0 and SR0 u exams changed.

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SIMULATION FACillTY REPORT Facility l Licensee: Fermi 2 Nuclear Power Plant .

Facility Licensee Docket No. 50-341 Operating Tests Administered At: Fermi 2 Nuclear Power Plant During the conduct of the simulator portion of the operating tests, the following ~

item was observed:

1118 DESCRIPTION

1. Main Steam Line (MSL) radiation monitor failed to indicate an increase with a fuel element failure.
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