ML20042G839

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Advises That Reactor Operator & Senior Reactor Operator Operating Exams Scheduled for 900718.Ref Matl,Listed on Encl,Should Be Provided by 900604
ML20042G839
Person / Time
Site: Crane 
Issue date: 05/09/1990
From: Eselgroth P
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Hukill H
GENERAL PUBLIC UTILITIES CORP.
References
NUDOCS 9005160159
Download: ML20042G839 (5)


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MAY 91990 Docket No. 50-289 GPU Nuclear Corporation ATTN:- Mr. H. D. Hukill a

Vice President and Director of TMI-1 P. O. Box 480 Middletown, Pennsylvania 17057 Gentlemen:

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SUBJECT:

REACTOR OPERATOR AND SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS-In a telephone conversation between Mr. W. Thompson, Operations Training i

Manager, and Mr. B. Norris, Senior Operations Engineer, arrangements were made for.the administration of examinations at the Three Mile Island Nuclear -

Station, Unit 1.

The operating examinations are scheduled for July 18, 1990.

To meet the above schedule, it will be necessary for you to furnish the refer-ence material listed in Enclosure 1,." Reference Material-Requirements'for.

Reactor / Senior Reactor Operator Licensing Examinations,f' by June 4,1990. Any i

delay in receiving approved, p operly bound and indexed reference. material, or-the submittal of inadequate _ or incomplete reference material may result in the examination ~being rescheduled. Mr. Thompson has been advised of our reference material requirements, and the address where each set is to be mailed.

To better. document simulator examirat. ions, the Chief Examiner will have the I

simulator operator record predetermined plant' conditions (1,e., plant pressure',

temperature, pressurizer level, etc.),. for each simulator scenario.

The appli-cants will be responsible for providing this information, with any appeal of a.

simulator operating examination. Therefore, your training staff'should retain the original simulator examination. scenario information until all applicants-who took examinations'have either passed the operating examination, accepted the denial of their license, or= filed an appeal.

For the requalification re-examination, it is required that an employee be provided to complete the ext.mination team. The employee shall be an active (per the. requirements of 10 CFR 55.53(e) or (f))- SRO from the Operations Department..If desired by the facility, and agreed to by the Chief Examiner, additional employee.from the Training Department may be a member o.f the exami-nation team. This employee shall preferably be an active (per the requirements of -10 CFR 55.53(e) or (f)) SRO, but may be a facility or INP0 certified instructor. These individuals must not be scheduled-for an NRC administered examination during this visit, or participate as instructors once selected.

The facility representatives will be required to certify that they did.not knowingly compromise any portion of-the examination.

OFFICIAL RECORD COPY NORRIS/THI-1 90 DAY & REQUAL -_0001.0.0 9005160159 900509 05/04/90 PDR ADOCK 05000289 V

PDC

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GPU Nuc1' ear Corporation-2 The facility representative shall be restricted (1) from knowingly communicat-ing by any means the content or scope of the examination to unauthorized persons and (2) from participating in any facility programs such as instruc-tion, examination, or tutoring in which an identified requalification exami-nee (s) will be present. These restrictions shall apply ~after their first involvement with the examination or knowledge of its contents.

In addition to these individuals, the assignment of a' simulator operator'is requested I day prior to the scheduled examination date. The simulator opera'-

tor will be under examination security restrictions similar to those abeve, except that his/her restrictions shall apply from 1 day prior to the examina-tion date.

The completed senior reactor operator license application should be submittedL at least 30 days before the examination date so that we will be able to review the training and experience of the candidates, process'the medical certifica-tions, and prepare final examiner assignments after applicant eligibility; has i

been determined.

If the application is not received at least 30. days before 1

the examination dates, it is likely that a postponement' will be necessary.

Mr. Thompson has been informed of the above requirements.

This request is covered by Office of Management and Budget Clearance Number 3150-0101 which expires May 31,.1992. The estimated average burden is 7.7-hours per response, including gathering, xeroxing and' mailing the required material. Send comments regarding this burden estimate or any other aspect;of this collection of information, including suggestions for reducing this burden, to the Records and Reports Management Branch, Division of Information Support Services, Office of=Information Resources Management, U.S. Nuclear Regulatory Commission, Washington, D. C. 20555; and to the Paperwork Reduction Project-(3150-0101), Of fice-of Management and. Budget, Washington, D. C. ' 20503.

Thank you for your consideration in this matter.

If you have any: questions regarding the examination procedures and requirements, please contact the meat (215)337-5211.

Sincerely, Original Signed By:

PETER W. ESELGROTH Peter.W. Eselgroth, Chief PWR Section -

t Operations Branch Division of Reactor Safety

Enclosure:

Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations 0FFICIAL RECORD COPY NORRIS/TMI-1 90 DAY & REQUAL - 0001.0.1 05/04/90 i

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GPU Nuclear Corporation 3

cc w/ enc 1:

T. G. Broughton, Operations and Maintenance Director, TMI-1 C. W. Smyth, Manager, TMI-1 Licensing R. J. McGoey, Manager, PWR Licensing E. L. Blake, Jr., Esquire-TMI-Alert.(TMIA)

Susquehanna Valley Alliance (SVA)

W. Thompson, Operations Training Manager Public Document Room (PDR) i Local Public Document Room (LPDR)-

Nuclear Safety Information Center (NSIC)

NRC Resident Inspector Commonwealth of Pennsylvania bec w/ encl:

Management Assistant, ORMA (w/o enc 1)

B. Norris, DRS P. Eselgroth, DRS Chief Examiner Assigned Examiners' OL Facility File DRS Files (2) i l

i mg rath 05/ 7 /90 05/ 7 /90 i

l l-0FFICIAL RECORD COPY NORRIS/TMI-190 DAY & REQUAL - 0001.1.0

  • 05/02/90

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l ENCLOSURE 1 i

I REFERENCE MATERIAL REQUIREMENTS FOR REACTOR 0PERATOR LICENSING EXAMINATIONS l

1.

Complete Procedure Index (including surveillance procedures,-etc.)

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.All emergency procedures (emergency _ instructions, abnormalcor special pro-1 cedures) i 3.

Standing orders (important orders. that are safety.related ana may super-sede the regular procedures)-

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All annunciator / alarm response' procedures 5.

Emergency plan implementing procedures L

6.

Technical Specifications (and interpretations, if available) for all units L

for-which licenses ~are sought.

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7.

The-following on the plant reference simulation facility-a.

List of all preprogrammed initial conditions l

b.

List of all preset malfunctions with a clear identification number.

The list shall include cause and effect information.

Specifically, for each malfunction a concise description of the expected result, or range of results, that will occur upon implementation shall be provided. Additionally, an indication of.which annunciators are to be initially expected should be given, A description of simulator failure capabilities for valves,-breakers, c.

indicators and alarms.

d.

Where the capability. exists, an explanation of the ability to vary

' I the severity of a particular malfunction shall. be provided,, i.e.,

- ability to vary the size of a given LOCA or steam leak, or the 'abil-ity to cause a slow failure of.a component such as a feed pump, tur-

- i bine generator or major valve.

(e.g., drifting shut of_a_ main feed-L water control valve) l An identification of modeling conditions / problems that may-impact the e.

examination, 1

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Identification of any known performance test discrepancies not yet j

j correctec.

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Identification of differences between the simulator and the reference plant's control room h.

Copies of facility generated scenarios that expose the applicants to

-situations of degraded pressure control (PWR), degraded heat removal.

capability (PWR and BWR) and containment challenges ~(PWR and BWR).-

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-Simulator instructors manual.

(Voluntary by licensee).

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Description of the scenarios used for the training class.

The above reference material shall be approved, final issues and shall be so marked.

If a-plant has not: finalized some of-the material, the Chief Examiner shall verify with'the facility that.the most complete,'up-to-date material is available and that agreement has been reached with the licensee for;limitingL changes before the administration of the examination. All procedures and reference material shall be bound with appropriate indices or tables of-contents so that they can be used efficiently.

Failure to provide complete, properly bound and indexed plant reference material could result'in cancella-tion or rescheduling of the examinations.

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