ML17056A309
| ML17056A309 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 09/13/1989 |
| From: | Conte R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Burkhardt L NIAGARA MOHAWK POWER CORP. |
| References | |
| NUDOCS 8909260153 | |
| Download: ML17056A309 (14) | |
Text
REGULATORINFORMATION DISTRIBUTION lITEM (RIDS)
(ACCESSION NBR 8909260153 DOC.DATE: 89/09/13 NOTARIZED: NO FACIL:50-410 Nine Mile Point Nuclear Station, Unit 2, Niagara Moha AUTH.NAME AUTHOR AFFILIATION CONTEFR.J.
Region 1, Ofc of the Director RECIP.NAME RECIPIENT AFFILIATION BURKHARDT,L.
Niagara Mohawk Power Corp.
DOCKET N
05000410
SUBJECT:
Requests encl ref matls for reactor operator a senior reactor operator licensing exams scheduled for wk of 891127.
DISTRIBUTION CODE:
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TITLE: Operator Licensing Examination Reports NOTES:
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Docket No.: 50-410 SEP 18 1989 Niagara Mohawk Power Corporation ATTN:
Mr. Lawrence Burkhardt, III Executive Vice President Nuclear Operations 301 Plainfield Road
- Syracuse, New York 13212 Gentlemen:
SUBJECT:
REACTOR OPERATOR AND SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS In a telephone conversation between Mr. G. Weimer, Operations Training Super-
- visor, and Ms. T. Walker, Senior Operations
- Engineer, arrangements were made for the admini stration of licensing examinations at the Nine Mile Nuclear Power Station, Unit No. 2.
The operating examinations are scheduled for the week of November 27, 1989.
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,"
by October 16, 1989.
Any delay in receiving approved, properly bound and indexed reference material, or the submittal of inadequate or incomplete reference material may result in the examination being rescheduled.
Mr. Weimer has been advised of our refer-ence material requirements, and the address where each set is to be mailed.
To better document simulator examinations, the Chief Examiner will have the simulator operator record predetermined plant conditions (i.e., plant pressure, temperature, etc.), for each simulator scenario.
The applicants 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.
All license applications should be submitted at least 30 days before the examination date so that we will be able to review the training and experience of the applicants, process the medical certifications, and prepare final examiner assignments after applicant eligibility has been determined.
If the completed applications are not received at least 14 days before the exami-nation dates, it is likely that a postponement will be necessary.
Mr. Weimer 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 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> per response, including gathering, xeroxing and mailing the required 8909260i53 8909' PDR ADOCK 050004i0 V
PNU
Niagara Mohawk Power Corporation 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 In'formation Resources Management, U.S. Nuclear Regulatory Commission, Washington, D.
C. 20555; and to the Paperwork Reduction Project (3150-0101), Office 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 undersigned at (215) 337-5210.
Sincerely, priginal Signe6 Bg!
Richard J.
- Conte, Chief BWR Section Operations Branch Division of Reactor Safety
Enclosure:
Reference Material Requirements for Reactor/Senior Reactor Operator Licensing Examinations cc w/encl:
C.
V. Mangan, Senior Vice President D, Palmer, Acting Manager, Quality Assurance W. Hansen,
- Manager, Corporate Quality Assurance R. Smith, Unit 2 Superintendent, Operations C.
- Beckham, Manager, Nuclear Quality Assurance Operations R. Abbott, Unit 2 Station Superintendent J. Perry, Vice President, Quality Assurance K. Dahlberg, Unit 1 Station Superintendent R. Randall, Unit 1 Superintendent, Operations J
~ Willis, General Station Superintendent C. Terry, Vice President Nuclear Engineering and Licensing R. Seifried, Assistant Training Superintendent J.
- Warden, New York Consumer Protection Branch T. Conner, Jr.,
Esquire G. Wilson, Senior Attorney J. Keib, Esquire
- Director, Power Division, Department of Public Service, Sta State of New York, Department of Law Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector State of New York te of New York 0001.0.1 OFFICIAL RECORD COPY WALKER/NM2 90-DAY LTR./9/11/89-
Niagara Mohawk Power Corporation bcc w/encl:
Region I Docket Room (with concurrences)
Project Manager, NRR M. Slosson, NRR J.
- Dyer, EDO J. Wiggins, DRP D. Limroth, DRP R. Barkley, DRP T. Walker, DRS OL Facility File DRS Files (2) bcc w/o enclosure:
Management Assistant, DRMA ORS:RI
, P'alker/dmg
~p<9/~/89
/L DRS:RI Cont 0001.0.2 OFFICIAL RECORD COPY WALKER/NM2 90"DAY LTR./9/11/89-06/16/87
ENCLOSURE 1
REFERENCE MATERIAL REQUIREMENTS FOR REACTOR/SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS Existing learning objectives, Job Performance Measures and lesson plans (including training manuals, plant orientation manual, system descript-ions, reactor theory, thermodynamics, etc.)
A copy of the facility Job and Task Analysis (JTA), specifying the know-ledges and abilities required of an operator at the facility.
Each parti-cular knowledge and/or ability will include an importance rating correlat-ing i't to ensuring the health and the safety of the public. If a JTA is not furnished, the Knowledges and Abilities Catalog for Nuclear Power Plant Operators, NUREG 1122 (1123) will be used to establish content valid-ity for the examination.
All Job Performance Measures (JPMs) used to ascertain the competence of the operators in performing tasks within the control room comple-and, as identified in the facility JTAs, outside of the control room, i.e., local operations.
Training materials shall include all substantive written material used for preparing applicants for initial RO and SRO licensing.
The written mater" ial shall include learning objectives and the details presented during
- lectures, rather than outlines.
Training materials shall be identified by plant and unit, bound,
- abbed, and indexed.
System descriptions including descriptions of all operationally relevant flow paths, components, controls and instrumentation.
System training material should draw parallels to the actual proce-dures 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 anti-cipated operator error, maintenance
- error, and equipment failure.
Training material used to clarify and strengthen understanding of emergency operating procedures.
2.
Complete Procedure Index (including surveillance procedures, etc.)
3.
5.
All Administrative Procedures (as applicable to reactor operation or safety)
All integrated plant procedures (normal or general operating procedures)
All emergency procedures (emergency instructions, abnormal or special pro-cedures)
\\ ~
6.
Standing orders (important orders that are safety related and may super-sede 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 proce-
- dure, when appropriate)-
9.
All annunciator/alarm procedures 10.
Radiation protection manual (radiation control manual or procedures) 11.
Emergency plan implementing procedures 12.
Technical Specifications (and interpretations, if available)
System Operating Procedures 14.
Techni.al Data Book, and/or Plant curve information as used by operators and facility precautions, limitations, and set points (PLS) for the facility 15.
Licensee Event Reports for the previous two years.
16, The following on the plant reference simulation facility a.
List of all preprogrammed initial conditions 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 wi 1T occur upon implementation shall be provided.
Additionally, an indication of which annunciators are to be initially expected should be given.
c.
A description of simulator failure 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 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-bine generator or major valve.
(e.g., drifting shut of a main feed-water 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.
J
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).
(Voluntary by licensee).
i.
Simulator instructors manual (voluntary by licensee).
j.
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 limiting changes before the administration of the examination.
All procedures and reference mato.rial shall be bound with appropriate indices or tables of contents so that they can be used efficiently.
Failure to provid~ complete, properly bound and inde"ed plant reference material could result in cance"ila-tion or rescheduling of the xaminations.
'l