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UNITED STATES
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{. h' yg, o NUCLEAR REGULATORY COMA. 3SION t
WASHINGTON, D. C. 20$55 MA'l 12 1980 Indiana & Michigan Power Company ATIN: Mr. D. V. Shaller Plant Manager D. C. Cook Nuclear Plant P. O. Box 458 Bridgman, Michigan 49106 Gentlemen:
'Ihe U. S. Nuclear Regulatory rmmission (NRC) presently has underway a program to reassess iti requirenents regarding selection, training and licensing of all categories of personnel involved in the operation and unintenance of nuclear power plants. As a part of this pro organization, Analysis & Technology, gram, the NRC has contracted an outside Inc., to provide an indepen&nt perspec-tive regarding the requirements for operator licensing. In support of this effort, a survey team frcxn Analysis & Technology will visit selected reactor sites and sin dator facilities during the period of May 14 to June ~27, 1980.
D. C. Cook Nuclear Plant has been selected as one of the sites. Analysis &
Technology would like to visit the site June 16 - 18, 1980.
Me objective of these visits will be to collect information on NRC/ industry requirements and practices regarding the selection, prescreening, training, exadnation, requalification and performance of control rocan operators, senior operators and other operational and maintenare;e personnel. Selection of these sites was based on a desire that they be representative of all existing facil-lities and provide an adequate sampling 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 sampling of industry-wide practices for m bsequent analysis.
The results of this analysis will lead to res-m4Hnns for changes to NRC/
industry practices (where appwgiiate) which will provide increased assurance of the operational safety of nuclear power plants. The major parts of these surveys will consist of document research and personnel interviews. Survey tea =s will consist of frcxn two to five people.
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.- UNf 1 2 3939 Enclosure (1) provides a list of specific docut9entation desired to be made available, a list of personnel desired for interviews and additional suoport required for both reactor site and sinulator facility visits. In addition, a pronosed general schedule for the -wh+ of these visits is included.
A vital part of this research will consist of the deter:dr.ation of predictive indices of operator and trainee podmw.r_e based on a collection of data fra review of porma 1 training, performance and background records. 'Ihese pre-dictive im*4caa will be used in the evaluation of selection and prescreening criteria and dee-mination of prerequisites for advarmit. Analysis & Tech-nology per.uanti are authorized by the NRC to review these records. It is fully realized that these reemde are considered to be of a confidential nature.
To raintain this confidentiality, prior to departure frmt the site, information collected frcm these records will be correlated to an individual by use of a letter-nimber code rather than the use of an individual's nee, social security
- tuser, etc.--Similarly, any infm=Hm 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 aMnistrative procedures in granting release of these types of information (confidential ard/or proprietary) to Analysis & Technology survey personnel.
Your c.ecperetion in this effort is oup eciated. If any cuestions arise, or the scheduled dates for visiting the sites are not satisfactory, please con-tact e.vself or it. Joseph Buzy at (301) 492-7486. For your information, un have requested a final rc:xrt from Analysis & Technology by ed.d-dew 1980.
Werefore, it is necessary to complete the site visits by the end of June.
Sincerely, Paul F. Collins, Chief Operator Licensing Branch Division of Fmen Factors Safety i
Faclosure:
Informaticri Sources and Support Required for Reactor Site and Distribution:
Sim1ator Facility visits OLB Facility File OLB R/F cc w/o enclosures:
PFCollins Mr. Imrry T. Davis IE Resident Inspector Aralysis & Technology, Inc.
Technology Park P. O. Box 220 Porth Stanfrgton, Connac*4' + 06359 s
OF F.*;E h.00fbs.0LO L suRNaue.>,.pFConi s:31$
Onrn>I.5//?~l80.
.RC FORM 318 (9 74) NRCM Q240 A*U.S.GQVERNMENT PRINTING OFFICE: 1979-289-369