ML20234C433
| ML20234C433 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 09/14/1987 |
| From: | Pate R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Lindblad W PORTLAND GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 8709210286 | |
| Download: ML20234C433 (5) | |
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1 September. 14, 1987 m
' Mr.: Wil'11am J. Lindblad, President Por.tland General Electric Company 121.S. W.. Salmon Street.
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' Portland, Oregon-97204
Dear Mr.- Lindblad:
Subject:
' Reactor Operator Licensing. Examination In a> telephone conversation between Mr. Gary Ellis, Licensed Operator m
Instructor and Mr.i Philip'Morrill, Operator Licensing Examiner, arrangements were made for the administration of an operating examination at the Trojan Nuclear Power Plant.
The examination is scheduled for October 8, 1987.
It' is our understanding that most of the reference material previously forwarded to usLfor the-May 28, 1987 examinations is'still valid; consequently, only reference material which has changed needs-to be provided.. In' order for us to meet the above schedule, it will be necessary for the facility to furnish revisions _ to.the approved reference material listed in Attachment 1, " Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations," by September 15, 1987. Any delay in receiving properly bound 'and indexed reference material will' result in a delay in administering the examinations. Our examinations are. scheduled'far in advance' with considerable planning to utilize our present limited examiner manpower and to meet the examination dates requested by the various facilities. Therefore, missing the September 15, 1987 deadline, even by a few days, likely will result.in a long delay because it may not be possible to reschedule examinations at other facilities. Mr. Ellis has
'been advised of our reference material that is. required, and the examiner's name and address where the material is to be mailed.
Reactor Operator and Senior Operator license applications are normally be submitted at least 60. days before the first examination dates so that we will be able to review the training and experience of the candidates, process the medical certifications, and prepare final examiner assignments after candidate eligibility has been determined.
For this examination we require the Reactor Operator License application on or before September 28, 1987.
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B709210286 870914 I DR ADOCK 050
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Mr. William J. Lindblad 2
September 14, 1987 i
l This request for information was approved by the Office of Management and Budget under Clearance Number 3150-0101, which expires May 31, 1989. Comments on burden and duplication 'may be directed to the Office of Management and Budget, Repoyts Managcoent Room 3208 New Executive Office Building, Washington, D.C. 20503.
Thank you for~your consideration in this matter.
If you have any questions, please contact Mr. John Elin or Mr. Philip Morrill in Region V (415-943-3700).
Sincerely,
/s/
Robert J. Pate, Chief Reactor Safety Branch
Attachment:
1.
Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations cc w/o attachment (1):
R. Barr, SRI R. Pate, RV P. Morrill, RV J. Elin, RV R. Cross, RV (2 copies)
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I ATTACHMENT 1 I
l REFERENCE MATERIAL REQUIREMENTS FOR REACTOR / SENIOR REACTOR l
OPERATOR LICENSING EXAMINATIONS j
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1.
Existinglearningobjectivesandlessonplans(includingtraining i
manuals, plant orientation manual, system descriptions, reactor j
theory, thermodynamics,etc.)
Training materials should include all substantive written material used for preparing candidates for initial R0 and SR0 licensing.
The written material should be inclusive of learning objectives and the details presented during' lecture, rather than outlines. Training materials should be identified by plant and unit, bound, and indexed.
Failure to provide complete properly bound and indexed plant reference material will result in canceling and rescheduling of the examinations.
Training materials which irjclude the following should be provided:
System descriptions including descriptions of all operationally relevant flow paths, components, controls and instrumentation.
System training material should draw parallels to the actual procedures used for operating the applicable system.
Complete and operationally useful descrip'tions of ail safety-system interactions and, where available, B0P system interactions under emergency and abnormal conditions, including consequences of anticipated operator error, maintenance error, and equipment failure.
Training material used to clarify and strengthen understanding of emergency operating procedures.
Comprehensive theory material that includes fundamentals in the area of theory of reactor operation, thermodynamics, heat -
transfer and fluid flow, as well a specific application to actual in-plant components.
For example, mechanical theory material on pumps should include pump theory as well as j
descriptions of how these principles actually apply to major plant pumps and the systems in which they are installed (i.e.,
Reactor Coolant Pumps, all ECCS pumps, Recirculation pumps, i
Feedwater pumps and Emergency Feedwater pumps). Reactor Theory material should include descriptions that draw explicit ties between the fundamentals and the actual operating limits followed in 'the plant (i.e., reactor theory material should contain explanations how principles relate to the actual curves used by operators to verify shutdcun margin or calculate I
an ECP).
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2.
Procedure Index (alphabetical by subject) 1 O
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. All administr tive procedures (as applicable to reactor operation
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4.
All integrated. plant procedures (normal or general operating i
I procedures)
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o 5.
Emergencyprocedures(emergencyinstructions, abnormal' ort 5pecial
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procedures) 6.
Standing orders (important orders that are 'afety related and may s
supersede the regular proced'res) u 7..
Fuel-handling and core-loading procedures, (initial core loading procedure,whenappropriate) j j
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8.
Annunciator procedures (alarm procedures, including set points) t
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I 9.
Radiation protection manual (radia ion control manual or procedures)'
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- 10. Emergency plan implementing procedures e/
j s'
- 11. Technical Specifications
- 12. System operating procedures
- 13. Piping and instrumentation diagrams, electrical single-line dia5 rams, or flow diagrams
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- 14. Technical Data Book, and/or plant curve information as used by operators and facility precautions, limitations, and set points (PLS) for the facility,
- 15. Questions and answers that the facility licensee has prepared j'
(voluntary by facility licensee)
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- 16. The following on the plant reference simulation facility a.
List.of all readily available initialization points.
List of all preset malfunctions with a clear identification number /
i b.
The list should 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 should be Additionally,anindicationofwhichannunciatorsareto(.,
provided.
be initially expected should be given.
c.
A description of simulator failure capabilities for valves, breakers, indicators and alarms.
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d.
Where.the capability exists, an explanation of the ability to vary the severity of. a particular. malfunction should be provided, i.e.,.
ability to vary the size of a given LOCA'or steam leak, or-the ability _'to cause a low. failure of a component such as'a feed pump, turbine; generator. or major valve (e.g., drifting shut of a main
- feedwater control valve.
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'An identification of modeling conditions / problems that may impact the examination.
- f.. ' Identification of any known Perfordiance Test Failures not yet completed.
g.
Identification of differences between the. simulator and the reference
. plant's control room, h.
.. Copies of' facility generated scenarios that expose the candidates to situations of degraded pressure control (PWR), degraded heat removal-capability (PWR.andBWR)andcontainmentchallenges(BWR)maybe
.provided (voluntary-by licensee).
1.
Simulator instructors manual (voluntary by licensee) j.
Descriptionoftilescenariosusedforthetrainingclass(voluntary g
bylicensee)
- 17. Additional material required by.the examiners to develop examinations -
that meet the requirements of these standards and the regulations.
't All above reference material should be approved, final issues and should 1
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 limiting changes before the administration of the examination.
All procedures and reference material should be bound with appropriate indexes or tables of contents so that they can be used efficie.ntly.
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