ML17284A579
| ML17284A579 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 10/28/1988 |
| From: | Wright G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Oxsen L WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| References | |
| NUDOCS 8811030401 | |
| Download: ML17284A579 (5) | |
Text
Docket No. 50-397 The Washington Public Power Supply System ATTN:
Mr. Lee Oxsen Assistant Managing Director for Operations 3000 George Washington Way Mail Drop 1023
- Richland, WA 99352 Gentlemen:
SUBJECT:
SENIOR OPERATOR LICENSING EXAMINATIONS In a telephone conversation between Mr. Bob Barmettlor, and Mr. John Bjorgen, arrangements were made for the administration of examinations at the WNP-2 Nuclear Plant.
The simulator examinations are scheduled for December 7, 1988.
In order for us to meet this schedule, it will be necessary for the facility to furnish the approved reference material listed in Enclosure I, "Reference Material Requirements for Reactor/Senior Reactor Operator Licensing Examinations" at least 15 days prior to the examination date.
Any delay in receiving approved properly bound and indexed reference material will result in a delay in administering the examinations.
Mr. Barmettlor has been advised of our reference material requirements, the number of reference material sets that are required, and the examiners'ames and addresses where each set is to be mailed.
To better document simulator examinations, the Chief Examiner will have the facility simulator operator record predetermined plant conditions (i.e., plant
- pressure, temperature, pressurizer level, etc.), for each simulator scenario.
The applicants will be responsible for providing this information, along with any appeal of a simulator operating examination.
Therefore, the facility training staff should retain the simulator examination scenario information until all applicants who took the examinations have either passed the operating examination, accepted the denial of their license, or filed an appeal.
All senior reactor operator license applications should be submitted at least 20 days prior to the first examination dates so that we will be able to review the training and experience of the applicants, process
- waivers, process the medical certifications, and prepare final examiner assignments after applicant eligibility has been determined.
If the applications are not received at least 15 days prior to the examination dates, it is likely that a postponement will be necessary.
8811030401 881028 PDR ADOCK 05000397 U
PDC p ()
Lee Oxen 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, Reports Management Room 3208, New Executive Office Building, 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 John Bjorgen at (312) 790-5559.
Sincerely,
": KY. C.. RR(gg-
.6i~)GiNC SlC)icp gy Geoffrey C. Wright, Chief Operations Branch
Enclosure:
1.
Reference Material Requirements for Reactor/Senior Reactor Operator Licensing Examinations cc w/enclosure:
B. Barmettlor, Plant Training Manager cc w/o enclosure:
R.
Sammworth, Project Manager, NRR K. E. Perkins, Branch Chief, OLB J. Elin, Section Chief, RV T. Meadows, Licensing Examiner, RV RI RIII RIII rgen/ib Jor a
ENCLOSURE I REFERENCE MATERIAL REQUIREMENTS FOR REACTOR/SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS l.
Existing learning objectives, Job Performance Measures and lesson plans (including training manuals, plant orientation manual, system descriptions, reactor theory, thermodynamics, etc.)
Training materials should include all substantive written material used for preparing applicants for initial RO and SRO licensing.
The written material should include learning objectives and the details presented during lectures, 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 MAY RESULT IN THE RETURN OF THE MATERIAL TO THE PERSON WHO IS THE HIGHEST LEVEL OF CORPORATE MANAGEMENT WHO IS RESPONSIBLE FOR PLANT OPERATIONS (E.G.,
VICE PRESIDENT OF NUCLEAR OPERATIONS).
ACCOMPANYING THE MATERIAL WILL BE A COVER LETTER EXPLAINING THE DEFICIENCIES IN THE REFERENCE MATERIAL AND THE FACT THAT THIS WAS THE REASON THE EXAMINATIONS WERE CANCELLED OR POSTPONED.
Training materials which include 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, descriptions of all safety-system interactions
- and, where available, BOP 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 as specific application to actual in-plant components.
For ~exam 'le, mechanical theory material on pumps should include pump theory as well as 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
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 shutdown margin or calculate an ECP).
2.
Complete Procedure Index (including surveillance procedures, etc.)
3.
All administrative procedures (as applicable to reactor operation or
'afety) 4.
All integrated plant procedures (normal or general operating procedures) 5.
Emergency procedures (emergency instructions, abnormal or special procedures) 6.
Standing orders (important orders that are safety-related and may supersede the regular procedures) 7.
Surveillance procedures (procedures that are run frequently, i.e., weekly or that can be run on the simulator) 8.
Fuel-handling and core-loading procedures, (initial core-loading procedure, when appropriate) 9.
Annunciator/alarm procedures 10.
Radiation protection manual (radiation control manual or procedures) 11.
Emergency plan implementing procedures 12.
Technical Specifications (and interpretations, if available) 13.
System operating procedures 14.
Technical Data Book, and/or plant curve information as used by operators and facility precautions, limitations, and set points (PLS) for the faci 1 ity 15.
guestions and answers specific to the facility training program which may be used in the or operating examinations (voluntary by facility licensee) 16.
The following on the plant reference simulation facility a.
List of all preprogramed initial conditions b.
List of all preset malfunctions with a clear identification number.
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 provided.
Additionally, an indication of which annunciators are to be initially expected should be given.
c.
A description of simulator fai lure capabilities for valves,
- breakers, indicators and alarms
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 slow failure of a component such as a feed
- pump, turbine generator or major valve (e.g., drifting shut of a main feedwater control valve) e.
An identification of modeling conditions/problems that may impact the examination f.
Identification of any known performance test discrepancies not yet corrected g.
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) may be provided (voluntary by licensee) i.
Simulator instructors manual (voluntary by licensee) j.
Description of the scenarios used for the training class (voluntary by licensee) 18.
Additional material required by the examiners to develop examinations that meet the requirements of these Standards and the regulations.
The above reference material should be approved, final issues and should 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 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 cancellation or rescheduling of the examinations.