ML20063A313

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Informs of 800621-23 Site Visit by Analysis & Technology,Inc to Collect Info in Support of NRC Reassessment of Requirements Re Selection,Training & Licensing of Nuclear Power Plant Personnel.Cooperation Requested
ML20063A313
Person / Time
Site: 05000000, Indian Point
Issue date: 05/12/1980
From: Collins P
Office of Nuclear Reactor Regulation
To: Bayne J
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
Shared Package
ML093450149 List: ... further results
References
FOIA-80-515, FOIA-80-555 NUDOCS 8203030165
Download: ML20063A313 (2)


Text

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UNITED STATES g

3 [%&.,y[ g yy NUCLEAR REGULATORY COMMISSION g[,

l WASHINGTON, D. C. 20555

  • % ~,f ms 136' i 2 1530 Power Authority of the State of New York AT N: Mr. J. P. Bayne, Resident Manager Indian Point 3 Nuclear Power Plant P. O. Box 215 Buchanan, t'ew York 10511 Gentlemen:

The U. S. Nuclear Regulatory Ccxmission (NRC) presently has underway a progran to reassess its requirements regarding selection, training and licensing of all categories of personnel involved in the operation and maintenance of nuclear power 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 requireuents for operator licensing. In support of this effort, a survey team from Analysis & Technology will visit selected reactor sites and simlator facilities during the period of May 14 to June 27, 1980.

Indian Point, Unit No. 3 has been selected as one of the sites. Analysis &

Technology would like to visit the site May 21 - 23, 1980. This visit will coinctde with one to Indian Point, Unit No. 2 The objective of these visits will be to collect information on NRC/ industry requirements and practices regarding the selection, prescreening, training, erant+n, requalification and performance of control room operators, senior operators and other operational and maintenance 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 femd-f 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 reer==ndations for changes to NRC/

l industry practices (where swwgiate) which will provide increased assurance l

of the operational safety of nuclear power plants. The major parts of these i

surveys will consist of document research and personnel interviews. Survey teans will consist of frcxn two to five people.

e203030165 810804 PDR FOIA MADDEN 80-555 PDR

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  • UNf 121930 Enclosure (1) provides a list of specific doctrentation desired to be trade available, a list of personnel desired for interviews and additional support required for both reactor site and sinulator facility visits. In addition, a pronosed pencral schedule for the conduct of these visits is included.

A vital part of this research will consist of the deteruination of predictive indices of operator and trainee performance based on a collection of data from review of personnel training, performance and background records. '!hese pre-dictive indices will be used in the evaluation of selection and prescraaning criteria and deterudnation of prerequisites for advsncou ut.

Analysis & Tech-nology personnel are authorized by the NRC to review these records. It is fully realized that these reemii are considered to be of a confidential nature.

To maintain this confidanH=11ty, prior to departure frcm the site, information collected frcm these records will be correlated to an individual by use of a letter-ntrnber code rather than the use of an individual's nane, social sec 2rity

- rn*er,-etc.---Sirdlarly, any infmu tion 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 p= - a.El.

Your cooperation in this effort is appreciated. If any ouestions arise, or the scheduled dates for visiting the sites are not satisfactory, please con-tact myself or 12. Joseph Buzy at (301) 492-7486. For your information, we have r'equested a final report from Analysis & Technology by mid-D* 1980.

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

Sincerely, Paul F. Collins, G ief Operator Licensfrg Branch Division of Ftran Factors Safety

Enclosure:

Information Sources and Supoort Required for Faarme Site and Distribution:

Sim1stor Facility visits OLB Facility File OLB R/F cc w/o enclosures:

PFCollins it. Iarry T. Davis IE Resident Inspector Analysis & Technology, Inc.

Technology Park P. O. Box 220 North Stonington, prHmc 06359 s

Orrice >.DRES:.0LS f suRNar. ef.PFCoMi s:31$ -

Care >l.,5/ & 80.

nac FORM 318 (9 741 NRCM C240 A*U.S. GOVERNMENT PRINTING OFFICES 1979-289 349

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