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MAY l 21930 Temessee Valley Authority ATIN: Mr. R. J. Johnson, Training Center Coordinator Sequoyah Nuclear Plant P. O. Box 2000 Daisy, Temessee 37319 Gentleren:
The U. S. Nuclear Regulatory rmmt asion (NRC) presently has underway a program to reassess its requirecents regar selection, training and licensing of all categories of personnel involved in operation and maintenance of nuclear powr plants. As a part of this program, the NRC has contracted an outside organization, Analysis & Technology, Inc., to provide an independent perspec-tive regarding the requirements for operator licensing. In support of this effort, a survey tean fra Analysis & Technology will visit selected reactor sites and simlator facilities during the period of Fay 14 to June 27, 1980.
The TVA Training Center been selected as one of the facilities. Analysis
& Technology muld like to visit the facility June 12 - 13, 1980.
l Ihe objective of these visits will be to collect information on NRC/ industry j
requirements and practices regarding the selection, prescreening, training, examination, requalification and performance of control rom operators, senior operators and other operational and maintenance personnel. Selection of these sites was based on a desire that they be repres'ent.ative of all existing facil-lities and provide an adequate sag ling of different training programs. It is in no way intended for these surveys to constitute an audit of an individual facility's practices, but rather, that they provide a sagling of industry-l wide practices for subsequent analysis.
l The results of this analysis will lead to recemmmdaHea for dwiges to NRC/
industry practices (where appropriate) which will provide incraaaad assurance of the operational safety of nuclear powr plants. The major parts of these surveys will consist of doc eent research and personnel interviews. Survey teams will consist of fra two to five people.
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l k$R 00fj31 sloso4 MADDEN 80-555 PDR
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MAY i e 180,
Enclosure (1) provides a list of specific documentation desired to be made available, a list of personnel desired for interviews and additional support required for both reactor site and sinulator facility visits. In addition, a proposed general schedule for the conduct of these visits is included.
A vital part of this research will consist of the determinaHm of predictive indices of operator and tre nee performance based on a collection of data fra d
review of personnel training, performance and background records. These pre-dictive indices will be used in the evaluation of selection and prescreening criteria and determinaHm of prerequisites for advancement. Analysis & Tech-nology personnel are authorized by the NRC to review these records. It is fully realized that these records are considered to be of a cmHdanHal nature.
To maineafn this confidanHality, prior to departure from the site, information collected from these records will be correlated to an individual by use of a letter-nunber code rather than the use of an individual's name, social security number, etc. Similarly, any information collected that is considered by the facility to be of a proprietary nature will be treated as such. Facilities are requested to follow their normal administrative procedures in granting release of these types of information (confidential and/or proprietary) to Analysis & Technology survey personnel.
Your cooperation in this effort is appreciated. If any questions arise, or the scheduled dates for visiting the sites are not satisfactory, please con-tact myself or Mr. Joseph Buzy at (301) 492-7486. For your information, we have requested a final report from Analysis & Technology by mLd-December 1980.
Therefore, it is necessary to ccmplete the sire visits by the end of June.
Sincerely,
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2 F.Coklins,'Gief P
Operator Licensing Branch Division of Faznan Factors Safety
Enclosure:
Information Sources and Support Required for Reactor Site and Simlator Facility Visits cc w/o enclosures:
Mr. larry T. Davis Analysis & Technology, Inc.
Technology Park P. O. Box 220 l
North Stonington, Connecticut 06359
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