ML20063A092

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Informs of 800617-19 Site Visit by Analysis & Technology,Inc to Collect Info in Support of NRC Reasessment of Requirements Re Selection,Training & Licensing of Nuclear Power Plant Personnel.Cooperation Requested
ML20063A092
Person / Time
Site: 05000000, Calvert Cliffs
Issue date: 06/13/1980
From: Collins P
Office of Nuclear Reactor Regulation
To: Russell L
BALTIMORE GAS & ELECTRIC CO.
Shared Package
ML093450149 List: ... further results
References
FOIA-80-515, FOIA-80-555 NUDOCS 8203020736
Download: ML20063A092 (2)


Text

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.m JUN 131980 Baltirrre Cas & Electric rb:pany ATIN:

It. Ime Nssell, Plant l'anager, Calvert Cliffs l'.uclear Power Plant Gas & Electric Building Baltincre, l'arylarA 2I202

Dear l'r. Russell:

The U. S. Nuclear Regulatory Carission (13C) presently has underway a program to reassess its requircrents regarding selection, training and licensing of all categories of personnel involved in the operation and enintenance of neclear power plants. As a part of this program, the IRC has contracted an outside organization, Analysis & Technology, Inc., to provide an indepenc'ent perspec-tive regcrding the requirments for operator licensing. In support of this effort, a survey tean from Analysis & Technology will visit selected reactor sites and siculator facilities during the period of May 14 to June 27, 1980.

Calvert Cliffs Tower Plant has been selected as cne of the sites. Analysis &

l Technology umld like to visit the site June 17 - 19, 1980.

The objective of these visits will be to collect inferration on IIC/ industry requirements and pracefcaa regarding the selection, prescreening, training, examination, regmif fication and performance of control roan operators, senior operators and other operational and enintenance personrel. Selection of t. se sites ws based on a desire that they be representative of all existing fac.1-lities and provide an adequate samplirg of different training prograns. It is in no way intended for these surveys to constitute an audit of an indiv44=1 facility's practices, but rather, that they provide a sanpling of industry-wide practican for subsequent analysis.

h results of this analysis will lead to % =udations for changes to NRC/

industry practices (where appropriate) which will provide increased assurance cf the operational safety of nucicar power plants. h major parts of these surveys will consist of doctment research and personrel interviews. Survey teams will consist of from two to five people.

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. Enclosure (1) provides a list of specific doctrentaticn desired to be nada available, a list of personnel desired for interviews and additional support recuired for both reactor site and simintor facility visits. In addition, a proposed general schedule for the ccoduct of these visits is included.

A vital part of this research will consist of the determinaticn of predictive indices of operator and trainee perforrence based on a collection of data fract revicu of personnel training, perfor:mnce and background records. These pre-dictive indices will be used in the evaluation of selection and prescreening dtcria and detarr4 nation of prerequisites for advancecent. Analysis & Tech-nology persennel are authorired by the FS.C to review these records. It is fully ren1 M that these records are considered to be of a confidential nature.

To rnintain this confidentiality, prior to departure fra: the site, infonration collected fract these records will be correlated to an individual by use of a letter-ntrber code rather than the use of an individual's nane, social security nu:6cr, etc. Similarly, any information colheted that is considered by the facility to be of a proprietary nature will be treated as such. Facilities are requested to follow their norrni adctinistrative procedures in granting release of these types of information (confidential and/or proprietary) to A.alysis & 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 Puzy at (301) 492-7486. For your information, ue have requested a final report frcca Analysis & Technology by mid-Daca+er 1980.

Therefore, it is necessary to carglete the site visits by the end of June.

Sincerely, Paul F. Collins, Chief Operator Licensing Branch Division of Human Factors Safety

Enclosure:

Information Sources and Support DISTRIBUTION.:

Required for Reactor Site and PF Collins Sirulator Facility Visits RA WiIson OLB R/F ce v/o enclosures:

OLB F/F Mr. Iarry T. Davis Analysis & Tech 1 ology, Inc.

Technology Park P. O. Ecx 220

" orth Stenington, Ccenecticut 06359

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