ML20217P147

Office for Analysis and Evaluation of Operational DATA.1996 Annual Report

ML20217P147
Person / Time
Issue date:	12/31/1997
From:	NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
To:
References
NUREG-1272, NUREG-1272-V10-N03, NUREG-1272-V10-N3, NUDOCS 9805060124
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AVAILABILITY NOTICE Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following sources:

1. The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC 20555-0001

2. The Superintendent of Documents, U.S. Government Printing Office, P. O. Box 37082, Washington, DC 20402-9328

3. The National Technical Information Service, Springfield, VA 22161-0002 Although the listing that follows represents the majority of documents cited in NRC publica-tions, it is not intended to be exhaustive.

Referenced documents available for inspection and copying for a fee from the NRC Public Document Room include NRC correspondence and intemal NRC memoranda; NRC bulletins, circulars, information notices, inspection and investigation notices; licensee event reports; l

vendor reports and correspondence; Commission papers; and applicant and licensee docu-ments and correspondence.

The following documents in the NUREG series are available for purchase from the Government Printing Office: formal NRC staff and contractor reports, NRC-sponsored conference pro- {

ceedings, international agreement reports, granteo reports, and NRC booklets and bro-chures. Also available are regulatory guides, NRC regulations in the Code of Federal Regula-

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j tions, and Nuclear Regulatory Commission issuances.

}

Documents available from the National Technical information Service include NUREG-series reports and technical reports prepared by other Federal agencies and reports prepared by the l Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission.

i Documents available from public and special technical libraries include all open literature )

items, such as books, journal articles, and transactions. Federal Register notices, Federal and State legislation, and congressional reports can usually be obtained from these libraries.

Documents such as theses, dissertations, foreign reports and translations, and non-NRC con-ference proceedings are available for purchase from the organization sponsoring the publica-tion cited.

Single copies of NRC draft reports are available free, to the extent of supply, upon written request to the Office of Administration, Distribution and Mail Services Section, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001.

Copies of industry codes and standards used in a substantive manner in the NRC regulatory process are maintained at the NRC Library, Two White Flint North,11545 Rockville Pike, Rock- )

ville, MD 20852-2738, for use by the public. Codes and standards are usually copyrighted and may be purchased from the originating organization or, if they are American National Standards, from the Amert-n National Standards Institute,1430 Broadway, New York, NY 10018-3308.

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OFFICE FOR ANALYSIS and EVALUATION of OPERATIONAL DATA ANNUAL REPORT,1996

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DECEMBER 1997

Previous Reports in Series ne following semiannual or annual reports have been prepared by the Office for Analysis and Evaluation of Operational Data (AEOD).

e - . Semiannual Report, January - June 1984, AEOD/S405, September 1984 e Semiannual Report, July - December 1984, AEOD/S502, April 1985 e Annual Report 1985, AEOD/S601, April 1986 e Report to the U.S. Nuclear Regulatory Commission on Analysis and Evaluation ofOperational Data 1986,NUREG-1272, AEOD/S701, May 1987 e Report to the U.S. Nuclear Regulatory Commission on Analysis and Evaluation ofOperational Data 1987, NUREG-1272, AEOD/S804 -

Vol. 2, No.1, Power Reactors, October 1988

Vol. 2, No. 2, Nonreactors, October 1988 -

e Oficefor Analysis and Evaluation ofOperational Data 1988 Annual Report, NUREG-1272 Vol. 3, No.1, Power Reactors, June 1989 Vol. 3, No. 2, Nonreactors, June 1989 e Oplcefor Analysis andEvaluation ofOperational Data 1989 Annual Report, NUREG-1272 Vol. 4, No.1, Power Reactors, July 1990 Vol. 4, No. 2, Nonicactors, July 1990 e Oficefor Analysis and Evaluation of Operational Data 1990 Annual Report, NUREG-1272 Vol. 5, No.1, Power Reactors, July 1991 Vol. 5, No. 2, Nonreactors, July 1991

, e Oplcefor Analysis and Evaluation ofOperational Data 1991 Annual Report, NUREG-1272 L Vol. 6, No.1, Power Reactors, July 1992, Vol. 6, No. 2, Nonreactors, August 1992

• Oficefor Analysis and Evaluation of Operational Data 1992 Annual Report, NUREG-1272 Vol. 7, No.1, Power Reactors, July 1993 )

Vol. 7, No. 2, Nonreactors, October 1993 e Oficefor Analysis and Evaluation of Operational Data 1993 Annual Report, NUREG-1272 Vol. 8, No.1, Power Reactors, November 1994 Vol. 8, No. 2, Nuclear Materials, May 1995 e Oficefor Analysis and Evaluation ofOperational Data 1994-FY95 Annual Report, NUREG-1272 Vol. 9, No.1, Power Reactors, July 1996 Vol. 9, No. 2, Nuclear Materials, September 1996 Vol. 9, No. 3, Technical Training, September 1996 i

i ABSTRACT The United States (U.S.) Nuclear Regulatory and fiscal year 1995, NUREG-1272, Vol. 9, Commission's Office for Analysis and Nos.1-3.

Evaluation of Operational Data (AEOD) has published reports ofits activities since 1984. This report, NUREG-1272, Vol.10, No. 3, The first repon covered January through June of covers technical training and presents the 1984, and the second report covered July activities of the Technical Training Center in through December of 1984. After those first two fiscal year 1996 in support of the NRC's semiannual reports, AEOD published annual mission. NUREG-1272, Vol.10, No.1, covers  ;

reports ofits activities from 1985 through 1993. power reactors and presents an overview of the j Beginning with the report for 1986, AEOD fiscal year 1996 operating experience of the j Annual Reports have been published as nuclear power industry from the NRC NUREG-1272. Beginning with the report for perspective. NUREG-1272, Vol.10, No. 2, 1987, NUREG-1272 has been published in two covers nuclear materials and presents a avview parts, No. I covering power reactors and No. 2 of the events and concerns in fiscal year 1996 covering nonreactors (changed to " nuclear associated with the use oflicensed material in materials" with the 1993 report). AEOD non-power reactor applications. Throughout changed its annual report from a calendar year these reposts, whenever information is presented (CY) to a fiscal year report, and added part for a calendar year, it is so designated. Fiscal No. 3 covering technical training, beginning year information is designated by the four digits with the combined Annual Report for CY 1994 of the fiscal year.

NUREG-1272, Vol.10, No. 3 iii

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I CONTENTS

- A bstract . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . i i i Abbrev iat ions . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . v ii Executive Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ix L

! 1 Introd uction .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I

! 2 Technical Training Programs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 l 2.1 Reactor Technology Curriculum ................................... 3 2.2 Engineering Support Curriculun' .................................. 5 2.3 Probabilistic Risk Assessment (. ................................. 6 2.4 Radiation Protection Curriculum ................................... 7 2.5 Fuel Cycle Curriculum . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 i 2.6 Safeguards Curriculum . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . m . . . . . . 9 l 2.7 Regulatory Skills Curriculum . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 2.8 Agreement State Training . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . _10 l

I l 3 S imulator Projects . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 1 3.1 GE B WR/4 Simulator Project . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I1 3.2 Westinghouse Simulator Project . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I1 l 3.3 Combustion Engineering Simulator Project . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I1 3.4 Babcock and Wilcox Simulator Project .................................... I1 3.5 GE BWR/6 Simulator Project . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . 12 3.6 Simulator Hardware Maintenance ....................................... 12 3.7 Simulator Software Maintenance . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 l 3.8 Nuclear Engineering Workstation Simulator . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 4 Other Technical Training Activities ............................................ 13 l 4.1 Revision ofInspection Manual Chapters 1245 and 1246 . . . . . . . . . . . . . . . . . . . . . . 13

4.2 High Performance Computing .......................................... 13 l 4.3 Technical Assistance to Others . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 1

4.4 Lisbon Initiative Technical Assistance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 4.5 Professional Meeting Support . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 Appendices A Instructional-Hour Totals . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A- 1 B Student Totals by Course . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B- 1 i

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Figures ,

1 2.1' Technical Training Course Trends .............................................. 4 2.2 : Technical Training Course-Week Trends ......................................... 4 2.3 Technical Training Instructional-Hour Trends . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 l

1 4

NUREG-1272, Vol.10, No. 3 v i

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ABBREVIATIONS i

A N l ABHP American Board of Health Physics NDE nondestructive examination i AEOD Analysis and Evaluation of NEWS Nuclear Engineering Workstation Operational Data (NRC Office Simulator l for) NMSS Nuclear Material Safety and ANS American Nuclear Society Safeguards (NRC Office of)

ATS Agency Training System NRA Nuclear Regulatory Authority NRC Nuclear Regulatory Commission B NRR Nuclear Reactor Regulation (NRC l

B&W Babcock and Wilcox Corporation OfTice of)

BPR business process re-engineering BWR boilingewater reactor O OAS Organization of Agreement States C OIG Office of the Inspector General CE Combustion Engineering (NRC)  ;

Corporation

CFR Code ofFederalRegulations P COTS commercial off-the-shelf PIP PRA implementation Plan PRA probabilistic risk assessment l D PTFG PRA Training Focus Group DEC Digital Equipment Corporation R

E RES Nuclear Regulatory Research EOP emergency operating procedure (NRC Office of)

EP emergency preparedness l

ERIS Emergency Response Information S -

System SAT site access training .

SART site access refresher training G SGI Silicon Graphics intemational GE General Electric Corporation SPDS Safety Parameter Display System H U HRIS Human Resources information URTC Ukrainian Radiation Training System Center l I I&C instrumentation and control IMC inspection manual chapter i

! NUREG-1272, Vol.10, No. 3 vii l

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EXECUTIVE

SUMMARY

The Office for Analysis and Evaluation of on the revised 10 CFR Part 20; courses, course-Operational Data (AEOD) was created in 1979 weeks, and instructional hours continue to to provide a strong, independent capability to increase primarily as a result of adding new analyze and evaluate operational safety data curriculum areas in probabilistic risk assessment l associated with activities licensed by the U. S. and fuel cycle technology and the development l Nuclear Regulatory Commission (NRC). AEOD of new courses in these areas.

i is also responsible for the NRC's Incident Response, Incident Investigation, and Technical Reactor Technology Training Training Programs.

The core of the reactor technology training The Technical Training Program provides initial program continued to be an integrated series of and continuing technical training for NRC staff courses consisting of a three-week systems and contractors to satisfy training needs defined course, a two-week advanced course, and two by formal NRC staff qualification, development, weeks of reactor simulator training (one week of and training programs. Technical training which concentrates on emergency operating includes reactor technology programs and procedures (EOPs)). Cross training courses, specialized technical programs. Reactor simulator refresher training, and a variety of technology programs include a spectrum of other stand-alone reactor technology courses courses, including classroom and simulator have been made available to support NRC staff

! instruction, in each of the four Nuclear Steam qualification programs. Reactor technology

! Supply System vendor designs-General course students included a significant number of

! Electric (GE), Westinghouse, Combustion foreign and state regulatory personnel. Several Engineering (CE), and Babcock and Wilcox upgrades were made to the full course series to l (B&W). Specialized technical training is ncorporate more performance-based '

provided in engineering support, probabilistic instructional methods focusing on improving the risk assessment, radiation protection, fuel cycle regulatory skills of inspectors, and to tie the j l technology, safeguards, and regulatory skills- courses together more closely. A risk i management module was developed and added During 1996 AEOD presented 62 reactor to the technical issues section of the advanced technology courses and 107 specialized technology courses. The use of Emergency l technical training courses. This training was Action Levels and Event Classification Guides l accomplished in 82,462 instructional-hours, has been incorporated into the simulator where an instructional-hour is a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period of courses. In addition, the simulator examination training per student. Most of this technical methodology was revised to incorporate two l training was provided in support of qualification more performance-oriented examinations into programs fcr NRC technical staff. the course, rather than the one final static exam.

The numb- of reactor technology courses, course-weeks, and instructional-hours peaked m.

Engineering Support Training 1992, primarily as a result of an increase in reactor engineer intern training. They decreased A new c ntract fgr techm. cal assistance in specialized techmcal training was awarded m,

' from 1992 through 1995; in 1996, however, September 1996. New student manuals will be although the number of courses continued to ,

developed for the Nondestructive Examinat,on i decrease slightly, because ofincreased student Technology and Codes, and the Eddy Current registration the number of course-weeks and instructional hours increased. Specialized Tesdng cogrses. NUREG/BR-0227, " Guidance technical training instmctional hours increased f fessmnal Development of NRC Staff m Digital Instrumentation and Controls," was  ;

substantially in 1994 due to extensive training issued in June 1996. The NUREG provides a )

i NUREG-1272, Vol.10, No. 3 ix

AEOD Annuel Rspon,1996 Technical Training I

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summary of the training program recommended Radiation Worker Training courses at for NRC inspectors and technical personnel who headquarters, additional SART courses were will be involved in the review or inspection of conducted in Region I. The two week Health digital instrumentation and control systems or Physics Technology Course was revised and improvement or modification to current systems updated during 1996. A new format has been installed in safety related equipment associated adopted which includes daily quizzes in addition with nuclear power plants. to the final comprehensive examination. A new Introductory Health Physics Course was Probabilistic Risk Assessment conducted for the first time at NRC headquaners. This course was formerly Training conducted by Oak Ridge Institute for Science  ;

NUREG/BR-0228, " Guidance for Professional Development of NRC Staff in Regulatory Risk Analysis," was prepared to assist NRC line Fuel Cycle Training management in developing qualification and training programs for their staff. The document AEOD continued the development of a fuel addresses the three general skill levels (basic cycle technology curriculum requested by the NMSS Division of Fuel Cycle Safety and j user, advanced user, and expert practitioner) I required by NRC staff in the area of risk- Safeguards. NRC staff targeted for this training informed regulation and provides line include fuel facility inspectors, license management with recommendations on the reviewers, and headquarters and other staff who education, experience, training, and have regulatory oversight of fuel cycle facilities.

recommended course sequences that agency The planned curriculum consists of eight employees will need to use probabilistic risk courses that are being developed by various assessment (PRA) in theirjobs. During 1996 contractors. Instmetors include contractor two new courses were added to the PRA Personnel, subject matter expens within the training curriculum. The Accident Progression Depanment of Energy, and NRC expens from Analysis course was developed as a result of Job the regions and headquarters. NRC Inspection and Task Analyses performed by the NRC Manual Chapter (IMC) 1246 was revised to Offices of Nuclear Reactor Regulation (NRR) incorporate these new courses into the fuel and Nuclear Regulatory Research. This course facility inspector qualification program.

covers PRA Level 2 topics. A PRA for Technical Managers course was developed Regulatory Skills Training based on recommendations of the PRA Training Focus Group. This course is designed to provide At the request of the Office of the Inspector the technical manager with up-to-date General (OlG), AEOD developed the Field information on the uses of PRA within the Techniques and Regulatory Practices course for agency as well as an overview of PRA topics. OIG and the Office ofInvestigations. A final comprehensive review and dry run were Radiation Protection Training conducted in early December 1996. This course is presented using a workshop / case study The Site Access Training (SAT) manual was approach. It bridges the gap between formal revised to include material from the newly classroom training and real-world on-the-job issued Management Directive 10.131 as well as Performance, emphasizing trainee application of to reflect changes to 10 CFR Part 19 and the important, job-relevant skills and knowledge in revision of Regulatory Guide 8.29. In addition realistic case study scenarios.

to the routinely scheduled SAT, Site Access Refresher Training (SART), and Nuclear Material Safety and Safeguards (NMSS)

Executive Summary x NUREG-1272, Vol.10, No. 3

Technical Training AEOD Annual Repon,1996 Agreement State Training computer systems that serve as the simulator compute platforms was begun in 1996.

In 1996, for the last time, the NRC paid all the expenses of Agreement State students attending Babcock & Wilcox Simulator Project NRC-sponsored training courses. Of the 261 In 19% procurement of two replacement Encore students who attended 12 materials courses,64 RSX computer systems with an attached DEC percent of them were from Agreement States. A Alpha AXP was begun. This is similar in Training Working Group, consisting of NRC architecture to the system currently used on the and Organization of Agreement States BWR/4 simulator and to the one being procured personnel, has been established to address future for the Trojan simulator. A project was also Agreement State training issues. In anticipation initiated to replace the Aydir display system of a decline in the number of Agreement State with a system similar to that being procured for attendees when NRC funding is discontinued, the BWR/4 simulator.

only one presentation of each contracted course has been scheduled for 1997. State attendees Other Technical Training Activities will be registered on a space available basis.

Revision ofInspection Manual Chapters Simulator Projects 1245 and 1246 AEOD issued an extensive revision to NRC  !

GE BWR/4 Simulator Project IMC 1246 in June 1996, and NRR issued a Replacement of the computer system for the revision to IMC 1245 in December 19%. The BWR/4 simulator was completed in 1996. revisions allow each program office to function Upgrade of the BWR/4 Simulator Safety independently, give each office direct control Parameter Display System (SPDS) was over their qualification programs, and align the compieted in 1996. A project to replace the manual chapters with the regional organizations, aging Training Working Group Aydin Controls The revisions also address comments in recent video display system was begun in 1996. The OIG audits. The current category of " training display system is part of the process computer required within two years of cenification" has simulation. The system has been out of been removed and the layout improved to be production for several years. more compatible with the revised Agency Training System.

Westinghouse Simulator Project To improve reliability of the Trojan simulator, Lisbon Initiative Technical Assistance computer system peripherals were replaced with AEOD continued to provide technical training small computer serial interface devices in 1996. assistance to Russia and Ukraine. Under the The original Encore 32/9780 computers are framework of Russian Priority 5 of the Lisbon being replaced with Encore RSX computers Initiative, AEOD is helping Gosatomnadzor with an attached DEC Alpha AXP system.The (GAN) of Russia to establish a functional architecture is similar to that used on the training center and a comprehensive system for BWR/4 simulator. training and qualification of technical personnel. l During 19% AEOD assisted specialists at the l Combustion Engineering Simulator GAN training center in establishing a local area ,

Project network. Work to date on Priority 5 tasks has  !

The Macintosh-based instructor station was been very successful. Current plans call for further enhanced in 1996 by adding new completion of the technical assistance work of features such as parameter monitoring. Priority 5 in 1997. Under the framework of Procurement of computer system hardware and Ukrainian Priority 2 of the Lisbon Initiative, software support for the Silicon Graphics AEOD is helping the Nuclear Regulatory Authority (NRA) of the Ministry of NUREG-1272, Vol.10 No. 3 xi Executive Summary

AEOD Annual Report,1996 Technical Training Environmental Protection and Nuclear Safety of call for completion of the technical assistance Ukraine to establish of a comprehensive system work of this priority by the end of 1997. Under for training and qualification of NRA technical the framework of Prierities 2.1 and 5.1 of the personnel. The designation of the Ukrainian Lisbon Initiativc, AEOD will provide Analytical Radiation Training Center (URTC) as the Simulaters to NRA and GAN for training of training authority for NRA was a significant rer,uiatory personnel.

advance in improving training. Current plans Executive Summary xii NUREG-1272, Vol.10, No. 3

1 INTRODUCTION AEOD provides technical training for NRC Specialized technical training courses are personnel to satisfy integrated training needs implemented, maintained, and improved in defined by formal NRC staff qualification and engineering support, probabilistic risk I training programs. New courses are developed assessment, radiation protection, fuel cycle and existing courses are modified to meet new technology, safeguards, and regulatory skills, or changing requirements identified by Specialized technical training is provided headquarters and regional offices. Principles of through customized courses developed by the the systems approach to training are routinely staff, customized courses by contractors, used throughout the life cycle of the technical coordination of slots (training opportunities) in training courses. courses that are presented by other Government agencies, and the identification and promotion Technical training includes reactor technology of appropriate commercially available courses programs and specialized technical programs, that NRC personnel may attend as individual Reactor technology training courses are training opportunities. For many of the implemented, maintained, and improved in each contracted courses, NRC perspectives are i of the four reactor vendor designs - General provided by designated individuals from within Electric (GE), Westinghouse, Combustion the NRC staff.

Engineering (CE), and Babcock and Wilcox (B&W). The curriculum includes a spectrum of AEOD manages the Technical Training Center courses invohing both classroom and simulator (TTC) and usociated capital assets in training. Reactor technology courses are Chattanooga, Tennessee, where most of the typically presented by AEOD staff, who also technical training is conducted. TI'C staff also provide technical assistance in areas of expertise

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manage the operation, maintenance, and upgrade of each full-scope reactor simulator and to other NRC offices as well as to foreign associated computer equipment. regulatory counterparts. -l l

l NUREG-1272 Vol.10, No. 3 1

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l 2 TECHNICAL TRAINING PROGRAMS l l During 1996 AEOD presented 62 reactor decrease slightly, the number of course-weeks technology courses providing 94 course-weeks and instructional hours increased. Specialized j ofinstmetion, and 107 specialized technical technical training instnictional hours increased

! training courses providing 120 course-weeks of substantially in 1994 due to extensive training instruction. These courses include all those on the revised Title 10 of the Code ofFederal

listed in the Technical Training Division Course Regulations (CFR) Part 20; courses, course-Catalog. Course-weeks can be correlated to staff weeks, and instmetional hours continued to effort or contract dollars required to conduct increase primarily as a result of adding new l training. curriculum areas in probabilistic risk assessment l

(PRA) and fuel cycle technology and the These 214 course-weeks of training comprised development of new courses in these areas.

! 82,462 instructional hours, of which 27,294 were devoted to reactor technology training and 2.1 Reactor Technology 55,168 to specialized technical training. Most of

! this techmcal tram,ng was provided m support Curriculum of qualification and development programs for ..

l NRC technical staff. An instructional-hour is a me f the reactor technology trammg one hour period of training devoted to any of the Provided m support ofinitial qualification following activities: lecture, seminar, Pmgrams for NRC staff continued to be an discussion, problem solving session, quiz, integrated series of courses consisting of a examination, on-the-job training, laboratory 3 week systems course, a 2 week advanced c urse, and two weeks of reactor simulator exercise, programmed leaming, and simulation exercise. For example, a course of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> for training (one week of which concentrates on 10 students would constitute 160 instructional. emergency Operating procedures [EOPs]). Th,s i integrated training was available often hours. Instructional-hours can be correlated to i the time spent by the NRC staff attending throughout the year. Cross-training courses, technical training courses, not including the simulat r refresher training, and a variety of study time outside of class necessary for other stand-alone reactor technology courses successful completion of many of the courses. have been made available to support NRC staff qualification programs. Reactor technology Statistical trends in technical training are shown curse students included a significant number of in Figures 2.1 through 2.3. The data include all f reign and state regulatory personnel.

courses presented by, coordinated by, or arranged by the 'ITC staff. The graphs show the Curriculum development during 1996 m.volved Upgrade, enhancement, and maintenance of trends for both reactor technology and , ,

I specialized technical training for 1987 through cum matenals to support mcorporation of the 1996. The number of reactor technology Shoreham simulator mto the boiling-water

! courses, course-. weeks, and instructional-hours reactor (BWR)/4 curriculum, mcorporation of peaked in 1992, primarily as a result of an the Trojan simulator mto the Westinghouse

! increase in reactor engineer intern training. wricuham, W unpynentau,on of the new CE and B&W cross-trammg courses. Considerable i They decreased from 1992 through 1995, development of interactive plant system largely due to reduced NRC hiring, staff diagrams using the Nuclear Engineering reductions within AEOD, and reprogramming of Workstation Simulator (NEWS) was completed reactor technology resources to address pressing in the GE technology. These mteractive system needs in specialized technical training. In 1996 diagrams are used to enhance student there was increased student registration and, although the number of courses continued to understanding of system dynamics and mterfaces. A new technical issues chapter on NUREG-1272, Vol.10, No. 3 3  ;

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AEOD Annual Report,1996 Technical Training Technical Training Course TrencIs 120

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-*- Specialized Technical Training 0 l l l l l l l EEEE5EEEEE Figure 2.3 Technical Training Instructional Hour Trends j l

l Training Programs 4 NUREG-1272, Vol.10, No. 3

Technical Tr:.ining AEOD Annu11 Report,1996 shutdown plant problems was added to the one 2 week schedule. This gives more flexibility BWR/4 curriculum. to ensure adequate time for higher priority conditions / scenarios. Shutdown operations were Revision of Westinghouse course materials to expanded in simulator courses in response to support the incorporation of the newly current events and agency interest. Use of purchased and installed Trojan simulator into piping and instrument drawings to analyze plant the Westinghouse curriculum continued. Course problems was incorporated into the simulator manuals, graphic illustrations, transient curves, courses. Use of Emerge.ncy Action Levels and and exam bank questions were completed. Event Classification Guides has been Development is continuing on supporting incorporated into the simulator courses. In instructor lesson plans and new advanced course addition, the simulator examination manual chapters. Development of simulator test methodology was revised to incorporate two, and operating procedures, scenarios, and more performance-oriented examinations into instructor lesson plans to support simulator the course, rather than the one final static exam.

courses was completed. The new exam questions focus on one system, function, or area of the control board, have Several upgrades were made to the full course several static problems for identification by the l series to incorporate more performance-based students, and, in addition, ask several questions instructional methods focusing on improving about the system, function, and control board.

regulatory skills ofinspectors, and to tie the Examination questions cover several different courses together more closely. The changes for plant conditions and focus on safety the systems course involved adding simulator significance, technical specifications and/or system walkdowns each day emphasizing the regulatory actions required. This exam control room controls and indication for the methodology also includes examination of  ;

system (s) covered. This takes the students from accident conditions and EOPs, which had not l

the theoretical system description, purpose, and been previously included in the old static exams.

j design covered in the classroom, to a practical l - visual and mechanical review of the lecture Cross-training courses in Combustion material in the simulator. Another change in the Engineering and Babcock and Wilcox systems course was the elimination of the technologies were presented. As a result of high graded mid-course quiz, and implementation of demand for the CE cross-training course this several structured, but ungraded short written year, additional shifts were run to accommodate practice quizzes. nis provides several, more the large class size in the simulator portions of focused reviews in a less threatening setting. the course.

)

Practical class exercises for transient analysis 2.2 Engineering Support and technical specification usage had previously been added to the advanced technology courses, Curriculum and continue to be expanded and improved. A A new contract for techm. cal ass.is tance in risk management module was developed and Specialized techmcal training was awarded m, added to the technicalissues section of the September 1996. New student rnanuals will be advanced technology courses. This module is , ,

developed for the Nondestmetive Examination provided in the reactor technology full course (NDE) Technology and Codes and the Eddy series to give students insights and discussions regarding PRA use by licensees and the NRC in Cureta hsting (ECT) coynes. Other development will include mstructor guides for managing and assessing risk at the plants.

NDE, ECT, and the Welding and NDE Oveniew counes, nese cmines assist NRC In the simulator courses, the schedule was techmcal managers and other techmcal revised from two I week course schedules, to  !

NUREG-1272 Vol.10.No.3 5 Training Programs

AEOD Annual Repon,1996 Technical Training personnel in developing a general familiarity will address methods for conduct of an effective with metallurgy, welding, and nondestructive inspection of digital instmmentation and control examination technologies, including welding systems as well as upcoming technical issues fabrication, welding processes, welding such as radio frequency interference and inspection, ultrasonic testing, radiographic electromagnetic interference. The workshop is testing, eddy current testing, liquid penetrant planned as an annual event which will allow for testing, and magnetic particle testing. interaction and dissemination of technical information regarding the digital I&C issues NUREG/BR-0227, " Guidance for Professional facing the agency.

Development of NRC Staffin Digital Instrumentation and Controls," was issued in 2.3 Probabilistic Risk Assessment June 1996. The NUREG provides a summary of the suggested trammg program recommended Curriculum l for NRC inspectors and technical personnel that A PRA Tra. .mmg Focus Group (I'fFG) was will be involved in the review or inspection of established m early March 1995 to provide digital instrumentation and control systems or ,

guidance to ensure that agency PRA trammg improvements / modifications to current systems Supports the PRA Implementation Plan (PIP).

installed in safety related equipment associated The PTFG meludes representatives from l with nuclear power plants. This guidance AEOD, NRR, and the NRC Offices of Nuclear document is designed to allow the formulation Regulatory Research (RES) and Nuclear of a training program for individuals based on Matend Safety and Safeguards (NMSS). The their educational background and/or experience , , ,

PTFG mission is to provide recommendations in the area of digital technology.

and guidance on converging the PRA training Program to support the PIP; categories of NRC Commercially available courses added to techmcal staff for PRA expertise categones; suppon staff training in the area of digital knowledge, skills and abilitics needed by NRC instmmentation and controls were updated with staff to carry out the PIP; development programs the most recent courses available from the deemed necessary to achieve each PRA industry. Course topics include instrumentation expertise category; relative importance and and control fundamentals, process controls, ,

Pnonty of PRA trammg imtiatives; needs for industrial measurement and control, j b and task analyses for different categones of microptressor fundamentals, software NRC staff; agency PRA policy issues related to engineering, software verification and training; and monitonng implementation of validation, and programmable controllers. These PRA training program changes and courses are available to the staff as individual imp lementation of IrfFG recommendations.

training opportunities through *he NRC Form 368 process and are held by selected To ass.ist NRC line management .in developing commercial firms such as the Instrumentation qualification and training programs for their Society of America and General Physics.

staff, NUREG/BR-0228, " Guidance n,or Pmfessional Duelopment of NRC Staff in The Digital Instrumentation and Controls (I&C) ,

Regulatory Risk Analysis," was developed. The Work Group will hold a second Regulatory l

d cument addresses the three general groups of Perspectives Workshop in February 1997 at SE I*IS fbaric user, advanced user, and NRC headquarters. This workshop is a .

expert Practitioner) required by NRC staff in the cooperative effort with the NRC Office of area f risk-informed regulation and provides Nuclear Reactor Regulation (NRR), the regions, line management with recommendations on the j and AEOD. The workshop will give inspectors, needed training, recommended course reviewers, and project engineers a better l

i understanding of the digital upgrade process and Training Programs 6 NUREG-1272, Vol.10, No. 3

Technical Training . AEOD Annuel Report,1996 sequences, education, and experience that 2.4 Radiation Protection agency employees will need to use PRA in their Curriculum Jobs.

Five medical courses were presented in The PTFG also recommended several changes Houston,TX, m 1996 under a new 5 year to the PRA curriculum. The I day PRA c nuact. Two offerings of the Teletherapy and Overview course has been deleted from the Brachytherapy Course were presented. This curriculum. The PRA Fundamentals course c urse concentrates on the application of (which provides more information) is now the ,

radionuclides by the meidical profession in the first course in the PRA curriculum. The PRA ueatment of cancer. Primary emphas,is is placed Basics for Inspection Applications and PRA n c balt-60 teletherapy and high-dose-rate Basics for Licensing Project Managers courses rem te afterloading brachytherapy, with medical (which differed primarily in the workshop area) faciHty t urs an hands-on experience wn se have been consolidated into a single course ,

equiPment. Three offerings of the Diagnostic entitled PRA Basics for Regulatory and Therapeutic Nuclear Medicine course were Applications.Two new modules, Risk Implications of Configuration Management and Presented. This course concentrates on the Implications of Uncertainty, have been APP li cation ofinternally admimstered ,

radionuclides by the medical profession m the recommended for development and inclusion in dI"8" 8is and treatment of disease. Primary applicable courses. Testing in appropriate PRA emPh. asis is placed on understanding the courses also began in 1996.

terminology and becoming famihar with the large number of different procedures employed.

In 1996 two new courses were added to the PRA Medical facility tours and hands-on experience -

training curriculum. The Accident Progression .

with the equipment are essential parts of the Analysis course was developed as a result of job training, and task analyses done for NRR and RES. This course covers PRA Level 2 topics. The PRA for . . .

Two Transportation of Radioactive Matenals Technical Managers course was developed e urses were presented in 1996. One was based on recommendations of the PTFG.This e nducted in Region I at their request. The course is designed to provide technical curse manua1is under revision by the managers with up-to<iate information on the ,

uses of PRA within the ageracy as well as an c ntract rt mc rPorate revisions to 10 CFR Part 71 and 49 CFR regulations. A presentation overview of PRA topics. ,

of the I week Internal Dosimetry course was als conducted in Region I at their request. In Development of the Accident Consequence Analysis and External Events courses has been addition, a new 5 year contract for presentation f tk Safdy Aspects ofImhaseial Radiography delayed until 1997. The Accident Consequence was awarded in 1996.

Analysis course will provide students with PRA Level 3 information, and the External Events . .

A new 5 year Radiation Protection Delivery course will familiarize students with the risk .

Order Contract was awarded in 1996. This associated with external events. It will combine coneact covers the Internal Dosimetry course, portions of the existing Seismic Margins course the Radioactive Waste Management Course and with additional material dealing with fires, ,

se Heakh Physics Topical Review course as floods, tornadoes, hurricanes, transportation accidents, etc. well as any ther special needs courses withm the scope of this contract.

Three different Health Physics Topical Review courses were conducted in 1996. These courses NUREG-1272, Vol.10, No. 3 7 Training Progr ms

AEOD Annual Report,1996 Technicel Training are designed to cover subjects of current interest electrical, shutdown cooling system; to the agency. The first course is related to the containment spray and isohtion, etc.); licensee application of high-dose-rate mmote EP plans and the sixteen emergency planning i brachytherapy in medical practice. This training standards; emergency classification system; was requested by and coordinated with NMSS emergency action levels; scenario reviews; in response to the misadministration which protective action recommendations; licensee occursed in Indiana, PA, for which NUREG- audits; changes made to licensee emergency .

l 1480 was issued. The second course, requested plans; drills and exercises; the EP inspection by the regions and presented by a representative program; exercise objectives and scenarios; of NRR, related to the determination of biennial and off year exercises; the realism rule; environmental lower limits of detection. The state and local emergency plans; NRC interface

, third consisted of six 1 day transportation with the Federal Emergency Management

( seminars conducted in each region, the Walnut Agency; and interface with the NRC Incident l Creek Field Office, and headquarters during Response Center.

L 1996. These seminars covered the recent I

changes in 10 CFR Part 71 and 49 CFR 2.5 Fuel Cycle Curriculum transportation regulations.

Work continued on a major new training The Site Access Training (SAT) manual was initiative in the area of fuel cycle technology revised to include material from the newly requested by the Division of Fuel Cycle Safety issued MD 10.131 as well as to reflect changes and Safeguards within NMSS. NRC staff to 10 CFR Part 19 and the revision of targeted for this training include fuel facility l

Regulatory Guide 8.29. In addition to the inspectors, license reviewers, headquarters staff.

routinely scheduled SAT, Site Access Refresher and other personnel who have regulatcry Training (SART), and NMSS Radiation Worker oversight of fuel cycle facilities. The planned Training courses at headquarters, additional curriculum currently consists of eight courses:

SART courses were conducted in Region I at Fuel Cycle Technology, Hazards of Chemical their request. and Mechanical Fuel Cycle Processes, General Health Physics Practices for Fuel Cycle The 2 week Health Physics Technology Course Facilities, Management Systems and Structures was revised and updated in 1996. A new format pc. Regulators, Integrated Safety (Hazards) has been adopted which includes daily quizzes Analyses, Mechanics of Sampling and in addition to the final comprehensive Measurement for Fuel Cycle Facilities, Nuclear examination. A new Introductory Health Physics Criticality Safety, and Fire Protection for Fuel course was conducted for the first time at NRC Cycle Facilities. Seven of the eight courses headquarters. This course was formerly identified have been developed. A pilot conducted by the Oak Ridge Institute for presentation of the Hazards of Chemical and Science and Engineering. Mechanical Fuel Cycle Processes course was conducted during August 1995. The Fuel Cycle NRR and AEOD staff have started development Technology and the Nuclear Criticality Safety of a new Emergency Preparedness (EP) courses were presented in November and

. Technology course. This course will provide December,1995, respectively. The Mechanics participants with an understanding of emergency of Sampling and Measurement for Fuel Cycle preparedness fundamentals. Areas covered Facilities course was piloted in January 1996.

include the history of EP philosophy and The General Health Physics Practices for Fuel requirements; EP requirements (10 CFR Part 50 Cycle Facilities course was piloted in June and Appendix E); EP criteria and guidance (e.g., 1996, and the Fire Protection for Fuel Cycle Regulatory Guide 1.101 and NUREG-0654); Facilities course was conducted in October i basic plant systems important to EP (e.g., l Training Programs 8 NUREG-1272, Vol.10, No. 3

Technical Training AEOD Annual Report,1996 1996. NMSS sponsored a course on Hazards Inspection Refresher course was held in Analysis in September 1996. NMSS supported Region II.

work on the Management Systems and Structures for Regulators course. The courses Two presentations each of the Inspection are being developed by various contractors. Procedures and Licensing Practices and Instmetors include contrxtor personnel, subject Procedures course were conducted in 1996. A matter experts within the Department of Energy meeting was held in January 19% to update the  !

community, and NRC experts from the regions Inspection Procedures course. Further meetings and headquarters. NRC Inspection Manual have been temporarily delayed pending the Chapter (IMC) 1246 was revised to incorporate results of the NRC/ Organization of Agreement these new courses into the fuel facility inspector States (OAS) Training Working Group. A qualification program. meeting to propose major modifications to the Licensing Practices and Procedures Course has 2.6 Safeguards Curriculum been temporarily delayed pending the results of the pilot business process re-engineering (BPR)

A Safeguards Technology Refresher course (S. effort. Implementation of the changes developed 402) was presented in August 1996. AEOD during the BPR process is expected to have continues to work closely with other significant impact on the training of license reviewers.

government agencies to provide training for security and safeguards personnel.

Courses continued to be presented at regional I cati ns.There were five presentations of the 2.7 Regulatory Skills Curriculum reactor version of the Inspecting for Performance course and one presentation of the At the request of the Office of the Inspector materials version. In addition, the Root General (OlG), AEOD trainers developed and Cause/ Incident Investigation Workshop was conducted a course for OIG and Office of held once in each region and NRC headquarters.

Investigations personnel at the TI'C in

.. In September 1996 the Incident Investigation November 1996 Course topics meluded trammg Team training course was conducted with two of NRC inspectors, sources and location of Agreement State representatives in attendance.

regulations, an overview of boiling water and pressurized water reactors, the regulatory Development of the new Field Techniques and environment, professionalism, reactor and Regulatory Practices course was completed. A materials inspection and licensing programs, final comprehensive review and dry run is radiation protection issues for reactors, high and scheduled in early December 1996. This course low level waste, mdustrial radiography, medical is presented using a workshop / case study uses of byproduct material, fuel cycle issues, approach. It bridges the gap between formal transportation of radioactive materials, and classroom training and real-world on-the-job gamma arradiators, moisture density gauges, and performance, emphasizing student application of well logging. Classroom lectures were important, job-relevant skills and knowledge in supplemented by simulator tours and realistic case study scenarios. The course demonstrations and videos of various actic.es. provides students with the opportunity to apply AEOD is exploring the applicability of this knowledge and skills learned during previous course to a wider NRC audience. training and on-the-job experience. Emphasis will be placed on student application of The Fundamentals ofInspection course was important, job-relevant skills and knowledge in held at NRC headquarters in April 1996. A realistic, interesting scenarios.

Fundamentals of Inspection course was also held in Region III and a Fundamentals of NUREG-1272, Vol.10, No. 3 9 Training Programs

AEOD Annual Report,1996 TechnicalTraining 2.8 Agreement State Training c. Identify acceptable attemative training options, including the evaluation of In 1996, for the last time, the NRC paid all the technology and training methods that could be used to lower the cost of training courses.

expenses of Agreement State students attending NRC-sponsored training courses. During twelve major materials courses presented in 1996,261 Several meetings have already been conducted students received training. Of those students,64 and a final report is anticipated sometime in 1997- l l percent were from Agreement States.

An NRC/OAS Training Working Group has The Medical Uses of Radionuclides course. was been established to accomplish the following: deleted from the schedule and Agreement State students were integrated into the NRC

. a. Evaluate the proposed training courses and sponsored medical courses.

[

l training subject areas for the Agreement i State staff that are necessary to assure Two 5 week Applied Health Physics courses

! equivalency with NRC nequirements and were provided with the majority of attendees forward a recommendation to the OAS and from the Agreement States.

the NRC; In anticipation of a decline in the number of

b. Evaluate the NRC policy for passing /failing Agreement State attendees when NRC funding courses and determine an acceptable policy is discontinued, only one presentation of each and methods to implement a policy for the contracted course has been scheduled for 1997. i Agreement States; and State attendees will be registered on a space-avaliable basis.

Training Programs 10 NUREG-1272, Vol.10, No. 3

l l

i 3 SIMULATOR PROJECTS 3.1 GE BWR/4 Simulator Project NEWS software as the bases for the SPDS software.

A replacement computer system was procured ,

and installed for the BWR/4 simulator during 3.2 Westinghouse Simulator 1995. The last element of the project was Project completed in 1996 In the original system, a vector processor was used to execute the reactor Operation of the Trojan simulator continued core model. The vector processor was during 1996 with very little down time. To eliminated during 1996 by recompiling the improve reliability, computer system peripherals vector processor code and scheduling it for were replaced with SCSI devices during 1996.

execution on the main computer processors.

A project was initiated to procure replacement A project to replace the aging Aydin Controls compoter systems. The original systems are video display system was begun in 1996. The Encore 32/9780s which are nearing the end of display system is part of the process computer their service life. The replacement systems will simulation, and consists of a display generator be Encore RSX computers with an attached chassis, monitors, keyboard, and computer Digital Equipment Corporation (DEC) Alpha interface. The system has been out of production AXP system. The architecture is similar to that for several years. To replace the display system, used on the BWR/4 simulator, hardware and software was procured from Aydin Controls. The new hardware consists of a Hewlett Packard Umx-based computer with 3.3 Combustion Engineering accelerated graphics cards, monitors, keyboards, Simulator Project and mouse. The system communicates with the host computer via Ethemet. Software emulates The Macintosh-based instructor station was the functions of the original display generator. further enhanced during 1996 by adding new Systems were procured for the BWR/4 and features such as parameter monitoring.

B&W simulators, and implementation has been completed on the BWR/4 simulator. Several process controllers were replaced with new devices, as well as recorders and digital Upgrade of the BWR/4 Simulator Safety meters. These steps were taken to improve Parameter Display System (SPDS) was begun in hardware reliability.

1995 and completed in 1996. The new system is j comparable to the BWR/6 Emergency Response A project was initiated to procure computer i Information System (ERIS) (except it depicts a system hardware and software support for the f Mark II Containment). The Picasso graphics Silicon Graphics computer systems that serve as system was used to create the user interface (the the simulator compute platforms.

f

) displays). Each of three SPDS Stations consists of an X-terminal connected to one of the Silicon 3.4 Babcock and Wilcox Simulator Graphics International (SGI) Challenge Project computers, which is in turn connected to the BWR/4 (Encore) simulation computer via The project to upgrade the performance of the

) Ethernet to receive data. The SPDS software B&W simulator was completed in 1993. This i runs on the SGI and the Encore computers.

upgrade brought the B&W simulator core, Development time was sigmficantly reduced by thermal hydraulic and containment models to using the BWR/6 ERIS algorithms and the the current state-of-the-art simulation and I

NUREG-1272, Vol.10, No. 3 11

AEOD Annud Report,1996 TechnicalTraining provided additional capabilities in the A contract is in place for simulator hardware simulation of various accidents and plant maintenance. Use of a contractor for these operations, including mid-loop operations. services has greatly reduced AEOD simulator engineer involvement in routine hardware The upgrade substantially increased the maintenance, allowing more time for simulator computational capacity required to execute the engineers to address simulation engineering simulation models. However, there is very little projects.

spare time on the Encore 32/9780 computer system that serves as the computer platform. It 3.7 Simulator Software has been observed that on occasion the models have msufficient CPU time to complete m a Maintenance given cycle, which results in a halt of the The contract providing for s.imulator software models' support ended in 1996. This function is now being performed in-house using staff simulator A project to procure replacement computer engineers.

systems was initiated in 1996. The replacement system will consist of two Encore RSX computer systems, with an attached DEC Alpha 3.8 Nuclear Engineering AXP. This is similar in architecture to the Workstation Simulator system currently used on the BWR/4 simulator, and to the one planned for the Trojan simulator. Development of the Nuclear Engineering Workstation Simulator (NEWS) continued l A project was also initiated to replace the Aydin during 1996. Graphical display development for l display system with a system similar to that the different technologies continued to be l

being procured for the BWR/4 simulator. Once performed primarily by the Reactor Technology l this is complete, it will be possible to retire the Instructors who are members of the NEWS l

Encore 32/55 computer that is currently used for Work Group. The rate of picture development is the process computer. The 32/55 is dependent upon the instructors' work schedule l

l approximately 20 years old, and teaching load, the complexity of each picture, and the instructor's familiarity with 3.5 GE BWR/6 Simulator Project Picasso. Because of the teaching and course development load, there were very few new A project was initiated to replace the Aydin disp lays developed during the year for the display system with a system similar to that Pressurized-water reactor technologies.

being procured for the BWR/4 simulator. Once However, development of displays for the this is complete, it will be possible to retire the BWR/4 continued.

Encore 32/55 computer that is currently used for i the process computer and display control Because of other software development i systems. The Encore 32/55 is approximately 20 activities, work on the CE and BWR/4 simulator  ;

5 years old. NEWS connections has been delayed.

Completion of the CE simulator connection is 3.6 Simulator Hardware scheduled for early 1997. The BWR/4 simulator connection will then be developed, as the Ma.mtenance software developed for the communication between the BWR/4 simulator computers and There were no significant hardware failures the new SPDS can be used as the basis, thus during 1996, making development time fairly short. I Simulator Projects 12 NUREG-1272, Vol.10, No. 3

4 OTHER TECHNICAL TRAINING ACTIVITIES 4.1 Revision ofInspection Manual added in several parts of IMC 1245. The Root Cause/ Incident Investigation Workshop will be Chapters 1245 and 1246 required for all mspectors and the Reactor

. Safety course will be required for most AEOD issued an extensive revision to NRC .

IMC 1246 in June 1996, and NRR issued a inSPectoa revision to IMC 1245 in December 1996. The ,

revisions allow each program ofGee to function 4.2 High Performance Computing independently, give each office direct control >

over their qualification programs, and will align AEOD efforts in high performance computing

! the rr s ual chapters with the regional and open sptems continued to evolve. The i organizations. The revisions also address twelve Sun SPARCStations were upgraded to  ;

i comments in recent OIG audits. The current SPARCStation 20 processors, and the operating category of " training required within two years system has been upgraded to Solaris 2.3. The of certification" has been removed and the SPARCStations are used for the NEWS project layout improved to be more compatible with a and for access to the Intemet.

future electronic agency training system.

Required initial training will be divided into The CE Simulator continues to run on a Silicon three areas: self study and on-the-job training Graphics 4D/240 dual-processor platform, with l (the bulk of the qualification joumal activities); three upgraded Indigo workstations for display core training (formal training required of all and control.

j inspectors in a panicular field), and specialized training (courses required for personnel who Two eight-processor Silicon Graphics l

will inspect in specialized areas). Challenge-L computer systems, running the IRIX operating system, have seen extensive use.

IMC 1246 was established in 1994 to define The BWR/4 Simulator SPDS system was qualification requirements for Materials License developed using a Challenge server, and the Reviewers. In IMC 1246, the requirements for Challenge systems serve as the primary Network Fuel Facility Specialist Inspectors have been File System, Network Information System, and significantly expanded to include more process Domain Name Service servers for the AEOD oriented courses in recognition of NRC's added simulation network.

responsibilities under 10 CFR Part 76. NMSS also added sections to include more New acquisitions in 1996 included the Hewlett headquaners personnel. These include NMSS Packard systems being used for the Aydin Headquaners Transportation Packaging and Dry Controls display system replacement. In addition, a project was begun to obtain vendor f Storage Supplier Safety Inspectors, Fuel Cycle suppon for all Silicon Graphics equipment and i License Reviewers, and Division of Waste

> Management Inspectors and License Reviewers. software. Additionally, the NRC Office of

) Information Resources Management provided IMC 1245 has historically addressed the assistance in obtaining vendor support for qualification requirements of all inspectors . AEOD's Sun equipment and software.

regional, NRR, and NMSS. Its last major revision was in 1991. The latest revision of IMC The AEOD Senior Simulator Engineer serves as 1245 added sections for headquarters personnel. system administrator for all technical training New sections are expected for Reactor Unix-based equipment as well as the Encore Technical Specialistfream Member and Reactor equipnent.

EP or Health Physics Team Member. Additional refresher training requirements have also been NUREG-1272, Vol.10, No. 3 13 l

' AEOD Annual Report,1996 Technical Training 4.3 Technical Assistance to Others 4.4 Lisbon Initiative Technical Assistance Technical assistance was provided by AEOD technical training staff in a number of diverse AEOD continued to be actively involved in areas throughout the year. In support of the technical assistance to Russia and Ukraine under l Operator Licensing Branch of NRR, both GE the Lisbon Initiative.

and Westinghouse instructors played the role of license candidates, provided assistance in Work continued under the framework of establishing the exam scenarios, and validated Russian Priority 5 to assist Gosatomnadzor j the simulator scenarios of the examiners-in- (GAN) of Russia in the establishment of a j training during examination techniques courses. comprehensive system for training and qualification of GAN technical personnel and a AEOD technical training staff panicipated in the functional training center for GAN personnel in Maine Yankee Special Assessment Team and the Don Region. l continued to provide assistance to NMSS for its

]

BPR project associated with implementation of Methodologies used by the NRC have been l a redesigned materials licensing process. Staff made available to GAN training managers, also provided assistance to several regions on instructors, and regional personnel. These have questions raised during routine inspections and included the normal activities associated with provided technical reviews of materials for application of the principles of the systems l several offices. approach to training. NRC has also provided i equipment needed for training program and AEOD technical training staff is participating in course development, training presentation, the working group for the development of the methodological support, and management of the Human Resources area model of the NRC training syr, tem. Delivery of the office Enterprise Model. equipment, training equipment, computer hardware and software, and consumables to the AEOD technical training staff panicipated in a GAN training center was completed in working group assigned to assist in the September 1996.

development of an Agency Training System (ATS), a subsystem of the Human Resources As a result of technical assistance provided Information system (HRIS). A separate but through Priority 5, GAN has made significant related workgroup was also established to progress in the overall strengthening of its develop the functional requirements for the regulatory training program. A GAN regulatmy ATS. This effort was completely successful. training center has been established in the city Even though the ATS effort was discontinued, of Novovoronezh, Russia, within the Don the functional requirements developed became Region of GAN. This is the national training an integral part of a future HRIS effort. center of GAN in the sense that the 'ITC is the national training center of the NRC. Sufficient <

AEOD technical training staff panicipated in the space has been obtained to suppon the needs of working group assigned to develop the the GAN training center for the next couple of j requirements for the evaluation, acquisition, and years. The GAN training center has been staffed implementation of a commercial off-the-shelf with permanent personnel including some with (COTS) software package that would form the reactor inspection and radiation protection I foundation of an automated HRIS. The COTS expertise and experience. The first draft of an solution includes the functionalities necessary overall GAN inspector qualification document, for an agency trammg system. based on NRC IMC 1245 but customized to i reflect conditions within GAN, has been completed. Suitable funding has been made Training Activities 14 NUREG-1272, Vol.10, No. 3

TechnicalTraining AEOD Annu 1 R: port,1996 available within the GAN budget for principles of the systems approach to training, development of a number of courses that will transfer knowledge of contemporary information serve as the curriculum of the GAN training and technology to NRA specialists to center for the next couple of years. GAN supplement and enhance their knowledge and i training center personnel have created the skills in several scientific and engineering j statements of work for these courses which will specialties, and delivery of specialized be developed by knowledgeable personnel in equipment to NRA training locations necessary GAN headquaders, other GAN regions, and in support of development and implementation various institutes within Russia. of the regulatory training program. Two contracts were completed in 1996 to supply -

In 1996 AEOD technical training personnel office and training equipment and interactive continued assistance to specialists at the training laser videodisc workstations in support of center for GAN personnel in the establishment development and implementation of the of a local area network. A meeting was regulatory training program. Providing conducted in Novovoronezh, Russia, from May assistance in preparation of training manuals has 20 to 22,1996, to review the delivery of office been an effective way to transfer knowledge on {

equipment and training aids provided by the nuclear and radiation safety. Development of a NRC and to refine the implementation plan for nuclear safety manual, a radiation protection Priority 5. Seven senior managers and manual, and a Safety Aspects ofIndustrial specialists from Gosatomnadzor (GAN) of Radiography manual has resulted from this Russia visited the Technical Training Center, assistance. The designation of the Ukrainian the Region II Office, and the Sequoyah Nuclear Radiation Training Center (URTC) as the Plant September 16 to 20,1996. The purpose of training authority for the NRA was a significant the visit was for senior GAN regional personnel advance in improving training. URTC personnel to see first hand how the NRC trains inspectors have considerable expertise in training -

and to discuss GAN plans for implementing - development and delivery. Rapid regulatory small training organizations in each region. As a training improvements were a result. Both the result of budget constraints, GAN is unable to NRC and the NRA have agreed that assistance routinely send inspectors to the Training Center provided by the NRC in the areas of in Novovoronezh. GAN plans to send a few transference of training methodologies, instructors from each region to Novovoronezh development of training requirements, and the for training and then have these individuals acquisition of specialized office and training implement regional training programs. equipment have been highly successful. Current plans call for completion of the technical Work to date on Priority 5 tasks has been very assistance work of this priority by the end of successful. Current plans call for completion of 1997.

the technical assistance work of Priority 5 in 1997. In addition to the two Lisbon Initiative technical assistance projects mentioned above, two others Under the framework of Ukrainian Priority 2, have evolved. Under the framework of Russian AEOD is assisting Nuclear Regulatory Priority 5.1, the AEOD will be providing an Authority (NRA) of the Ministry of Analytical Simulator (s) to GAN for training of Environmental Protection and Nuclear Safety regulatory personnel. The scope of this technical

! (MEPNS) of Ukraine in the establishment of a assistance includes development of a statement I

comprehensive system for training and of work, establishment of a contract, contractor qualification of NRA technical personnel. The development of specialized simulation software, scope of this technical assistance includes and delivery of equipment. The work in this transfer of the methodology and practical priority also involves assisting GAN in assuring application of activities associated with rin that the Analytical Simulator (s)is functional NUREG-1272, Vol.10, No. 3 15 - Training Activities

AEOD Annual Report,1996 TechnicalTrcining and wiequately mpresent the intended reactor National Standards Institute 13.36 committee designs and includes training of designated " Core Training in Radiation Protection for i GAN staff who will use and maintain the Workers".

Analytical Simulator (s). It also includes the prioritized development of additional Analytical AEOD technical training staff participated in a Simulator software loads and establishment of symposium on Decontamination and Analytical Simulator hardware at different GAN Decommissioning sponsored by the American locations. Nuclear Society (ANS) in April 1996. AEOD staff also participated in international PRA Under the framework of Ukraine Priority 2.1, symposiums in Seoul, Korea, and the United AEOD will be providing an Analytical States, continued to attend Health Physics Simulator (s) to MEPNS for training of Society meetings, and attended special Electric regulatory personnel. The scope of work in this Power Research Institute workshops on steam area includes development of a statement of generators and a national symposium on digital work, establishment of a contract, contractor - instrumentation and control.

development of specialized simulation software, and delivery of equipment. The work in this AEOD technical training staff actively priority also involves assisting MEPNS in participated in the Enlarged Halden Program assuring that the Analytical Simulator (s) are Group Meeting on Man-Machine Systems functional and adequately represent the intended Research in May 1996. One of the AEOD reactor designs and includes training of simulator engineers presented the paper titled designated MEPNS staff who will use and " Upgrade of the Safety Parameter Display maintain the Analytical Simulator (s). It also System on the USNRC BWR/4 Simulator",

includes the prioritized development and implementation of additional Analytical The AEOD technical training staff participated Simulator software loads. in the 9th Power Plant Dynamics, Control and Testing Symposium in May 1996.

In support of these four Lisbon Initiative technical assistance priorities, a number of AEOD technical training staff pa:ticipated in the planning meetings have taken place in Russia, Society for Computer Simultaion Spring Multi-Ukraine, and the U. S. Conference in April 1996. The AEOD Technical Training Advisor served on the conference 4.5 Professional Meeting Support ommittee and as a session chair for two si.ssions and on a panel discussion.

AEOD technical training staff actively participated in professional meetings, The AEOD Technical Training Advisor actively

- particularly in the health physics and reactor participated in the International Topical simulation areas. AEOD senior health physicists Meetings on Probabilistic Safety Assessment in participated in a meeting of the American Board November 1995 and in September 1996. He also of Health Physics (ABHP) Part II Examination Participated in the ANS winter and spring Panel and attended the Health Physics Society meetings, leading a seminar on the NRC midyear and annual meetings. One AEOD maintenance rule at the winter meeting.

senior health physicist served as a member of the ABHP examination panel, another is a The AEOD Technical Advisor served on the member of the Health Physics Society national publication steering committee and Acadernic Education Committee and the Health national planning committee of the ANS. He Physics Society Plan Cobalt-56 Working Group, also served as a member of the Institute of and another is a member of the American Electrical and Electronics Engineers Rc. liability Prediction Standards committee, and as an Training Activities 16 NUREG-1272, Vol.10 No. 3

Technical Training AEOD Annu:1 Rtport,1996 evaluator for Electrical Engineering curriculum. Instrumentation, Control, and Human-Machine In addition he served on the program committee Interfaces Technologies, in May 1996, and for the International Topical on Nuclear Plant chaired one of the sessions.

l I

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l NUREG-1272, Vol.10, No. 3 17 Training Activitica

i APPENDIX A Instructional-Hour Totals i

l l

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l l

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CONTENTS Tables Page A-1 Reactor Technology Instructional-Hour Totals by Course Group . . . . . . . . . . . . . . . . . . . . . . - A-1 A-2 Reactor Technology Instructional-Hour Totals by Course ...........................A-2 A-3 Specialized Technical Training Instructional-Hour Totals by Course ..................A-3 Key QTY = Quantity of Courses C-W = Quantity of Course-Weeks IH = Instructional-Hours

1. S = Number of Students R1 = Region i R2 = Region 11 R3 = Region Ill R4 = Region IV NRR = Office of Nuclear Reactor Regulation AEOD = Office for Analysis and Evaluation of Operational Data NMSS = Office of Nuclear Material Safety and Safeguards RES = Office ofNuclear Regulatory Research CTR = NRC Contractors IP = International Programs Personnel (Foreign Nationals)

SP = State Programs i OTH = OtherNRC Offices or Other Agencies TOT = Total NUREG-1272, Vol.10, No. 3 A-lii

Technical Training AEOD Annual Rsport,1996 Table A-1 Reactor Technology Instructional-Hour Totals by Course Group Rt R2 R3 R4 NRR AEOD NMSS RES IP AS SP OTH TOT COURSE QTY C-W IH Ill IH IH IH IH IH IH IH IH IH IH IH General Electric Technology Technology (100 Level) 2 2 198 33 330 99 99 0 0 0 33 0 0 F 891 Technology (2001.evel) ' I 3 0 0 0 0 630 0 0 0 0 0 0 0 630 Technology (W) Level) 4 12 672 384 1.824 864 1.344 0 0 0 1,152  % 288 0 6.624 Technology (500 Level) 4 8 476 272 1,088 612 816 0 0 0 816 136 0 0 4.216 Simulator (Series) 14 26 385 420 1,190 700 875 0 0 0 805 70 70 105 4.620 Simulator Refresher 21 21 945 630 1,050 665 315 35 0 0 70 0 0 70 3,780 Nuclear Engineering 2 4 210 0 70 210 420 280 0 0 0 0 0 140 1,330 Technology Review 4 4 245 280 140 105 140 35 0 0 0 0 0 0 945 Maintenance Overview 4 4 306 408 238 272 204 68 0 0 0 0 0 0 1,4 %

Cross Training 2 6 285 285 380 285 95 95 0 0 0 0 0 0 1,425 Reactor Concepts 3 3 14 0 0 238 42 0 0 14 14 0 0 70 392 Perspectives on Reactor Safety 1 1 175 0 35 70 210 315 0 0 70 70 0 0 945 TOTALS 62 94 3.911 2.712 6.345 4.120 5.190 828 0 14 2.960 372 358 484 27.294 I i

i l

NUREG-1272, Vol.10, No. 3 A-l Instructional-Hour Data l

l

AEOD Annual Report,1996 Technical Training Table A-2 Reactor Technology Instructional-Hour Totals by Course RI R2 R3 R4 NRR AEOD NMSS RES IP AS SP OTil TOT COURSE QTY C.W Ill Ill 111 111 til til III til 11I Ill Ill 111 Ill General Electric Technology GE BWR/4 'lechnology (R-104B) i I 99 33 165 66 33 0 0 0 0 0 0 66 467 GE BWR/4 Technology (R-200B) 1 3 0 0 0 0 630 0 0 0 0 0 0 0 630 GE BWR/4 Technology (R-3048) 2 6 384 0 1,056 96 960 0 0 0 768 0 288 0 3,552 i GE BWR/4 Advanced Technology 2 4 272 0 544 68 612 0 0 0 544 68 0 0 2,108 GE BWR/4 Simulator 6 12 20 70 560 70 630 0 0 0 490 70 70 0 2,170 s GE BWR/4 Simulator Refresher 6 6 455 35 385 105 0 0 0 6 0 0 0 0 980 GE Nuclear Engineering 1 2 210 0 0 140 140 70 0 0 0 0 0 0 560 GE BWR/4 l'echnol Review 2 2 140 140 35 105 70 35 0 0 0 0 0 0 525 WestiTabouse Technology Westinghouse Technology (R-104P) I I 99 0 165 33 66 0 0 0 33 0 0 33 429 ,

Westinghouse Technology (R-304P) 2 6 288 384 768 768 384 0 0 0 784 96 0 0 3,072 Westinghouse Advanced Technology 2 4 204 272 544 544 204 0 0 0 272 68 0 0 2,108 Westinghouse Simulator (R-621P) 2 2 35 0 0 70 105 0 0 0 35 0 0 105 350 )

Westinghouse Simulator (R-624P) 6 12 140 350 630 560 140 0 0 0 280 0 0 0 ,2.100 Westinghouse Simulator Refresher 9 9 350 350 595 175 175 0 0 0 0 0 0 70 1,715 Westinghouse Nuclear Engineering i 2 0 0 70 70 280 210 0 0 0 0 0 140 770 Westinghouse Maintenance Overview 4 4 306 408 238 272 204 68 0 0 0 0 0 0 1,496 Westi ouse Technol Review 2 2 105 140 105 0 70 0 0 0 0 0 0 0 420 Combustion Engineering Technology CE Cross Training I 3 190 0 285 95 95 0 0 0 0 0 0 0 665 CE Simulator Refresher 4 4 105 140 0 385 140 35 0 0 0 0 0 0 805 Bibeoek & Wilcox Technology B&W Cross Training i 3 95 285 95 190 0 95 0 0 0 0 0 0 760 B&W Simulator Refresher 2 2 35 105 70 0 0 0 0 0 70 0 0 0 280 Generic Reactor Technology Reactor Concepts 3 3 14 0 0 238 42 0 0 14 14 0 0 70 392 Pers etives on Reactor Safety 1 1 175 0 35 /0 210 315 0 0 70 70 0 0 945 Reactor Technologv Totals 62- 94 3.911 2.712 6.345 4.120 5.190 828 0 14 2.960 372 358 484 27.294 1

Instructional-Hour Data A-2 NUREG-1272, Vol.10, No. 3

Technical Training AEOD Annual Report,1996 i

Table A-3 Specialized Technical Training Instructional-IIour Totals by Course RI R2 R3 R4 NRR AEOD NMSS RES IP AS SP OTil TOT COURSE QTV C-W Ill ill III Ill III Ill III III III Ill III III III Prclubilistic Risk Assessment Probability & Statistics for PRA 2 2 140 105 105 105 525 140 0 105 35 0 0 35 1,295 PRA Basics for Regulatory App!ications 5 5 252 84 273 42 483 21 42 42 441 0 0 63 1,743 PRA Insights into IPEs 5 5 70 350 448 42 196 14 0 84 28 28 0 0 1,260_

System Modeling Techniques 2 2 84 56 84 56 280 112 0 28 56 0 0 28 ,84 IRRAS Basics 2 2 112 56 56 56 336 84 0 28 28 0 0 0 756 Advanced IRRAS 2' 2 84 56 56 56 196 R4 0 56 56 0 0 0 644 Iluman Reliability Assessment i I 21 63 42 63 42 21 0 21 0 0 0 21 294 Risk Assessment in Event Evt.ulation 2 2 63 147 42 21 210 42 0 21 0 0 0 0 546

) 'A Ergineering Support Power Plant Engineering I 3 102 102 102 0 612 0 0 102 0 0 0 306 1,326 Emergency Diesel Generators 2 2 416 32 384 96 32 64 0 0 0 0 0 0 1,024 Motorized Valve Actuators I l 64 0 96 0 64 0 0 0 0 0 0 0 224 Welding Technology & Codes 1 2 6,7 0 134 0 201 0 0 0 0 0 0 0 402 Di italI&C Worksh l l 120 40 30 80 240 160 0 40 0 0 0 40 800 Redittion Protection Site AccessTraining 4 4 0 0 0 14 308 28 196 14 0 0 0 56 616 Site Access Refresher Training 8 8 217 0 0 0 693 49 182 0 0 0 0 0 1,141 Radiation Worker Training 2 2 0 0 0 0 0 0 36 0 0 0 0 0 36 In Place Filter Testing Workshop 1 1 0 32 0 0 0 0 0 0 0 0 0 0 32 Applied IIcalth Physics 2 10 0 344 0 0 0 0 688 0 0 0 7,052 0 8,084 Environmental Monitoring 1 1 140 0 0 105 0 0 35 0 0 420 0 0 700 Introduction to llealth Physics i I O O O 35 35 0 385 0 35 35 0 105 630 Ipalth Physics Engineering 1 I O 35 _0 0 0 0 0 0 0 0 840 0 875 I Rad. Surveys in Support of Decomm. 2 2 210 0 14 56 98 0 364 0 0 0 0 0 742 Health Physics Technology 2 4 67 67 402 402 0 67 0 0 67 2077 0 0 3,149 ,

l Rad. Emergency Response and Oper. 2 2 0 32 0 64 0 0 0 0 0 0 0 0  %

Diag. & Thera. Nuclear Medicine 3 3 320 80 320 120 0 0 120 0 40 1,000 0 40 2,040 Rt.diological Accident Assessment 2 2 32 0 0 64 64 0 0 0 0 0 0 0 160 Transportation of Radiological Materials 2 2 560 0 315 70 0 0 105 35 0 490 560 0 2,135 Respiratory Protection 3 3 35 0 105 210 0 0 0 0 0 0 0 0 350 Internal Dosimetry & Whole Body Ctg. I 1 805 0 210 35 0 0 0 0 0 0 0 0 1,050 Teletherapy & Brachytherapy 2 2 120 0 280 0 0 0 80 0 0 840 0 0 1,320 Safety Aspects of Well Logging 1 1 0 0 72 36 0 0 144 0 0 576 0 0 828 Ilealth Physics T ical Review 1I i1 1,344 525 1,218 1.050 0 0 168 0 0 1,575 0 42 5,922 NUREG-1272, Vol.10, No. 3 A-3 Instructional-Hour Data

AEOD Annual Report,1996 Technical Training Table A-3 Specialized Technical Training Instructional-Hour Totals by Course Rt R2 R3 R4 NRR AEOD NMSS RESf IP AS SPI OTil' TOT COURSE QTY C-W 111 III Ill III III III III III III Ill Ill III Ill Fuel Cycle Technology {

Nuclear Criticality Safety 1 1 0 0 70 0 0 35 490 0 0 0 0 35 630 Gen. IIP Practices for Fuel Cycle Fac. I I O 112 84 56 0 28 476 0 0 0 0 0 756 Fuel Cycle Technology 1 I O 28 56 28 0 0 280 56 0 0 0 0 448 Mech. of Sam & Measurement I 1 0 84 56 84 28 0 420 0 0 0 0 28 700 Saferrards 1 Sr. ards Technol Refresher i 1 140 140 105 105 385 0 70 35 0 0 0 0 980 f l

Regylitory Skills Fundimentals ofInspection i I 84 28 168 84 308 56 224 0 0 0 0 112 1.064 Non Power Reactor i 1 64 32 32 32 0 0 0 32 160 0 0 32 384 Examination Techniques i I O 67 201 0 0 0 0 0 134 0 0 67 469 Inspection Procedures 2 2 0 0 144 36 36 0 72 0 0 1,332 36 180 1,836 Licensing Practices & Procedures 2 2 36 144 36 0 0 0 252 0 0 1,332 0 216 2.016 OSHA Introctrination 3 3 12 4 24 308 96 12 28 0 0 0 0 0 484 RootCause/ Incident invest Workshop 5 $ 245 350 630 245 175 70 385 0 210 0 0 70 2,380 lluman Performance Invest.

Workshop 2 2 49 0 140 0 21 0 0 0 0 0 0 7 217 Inspecting for Perfornn nce 6 6 108 288 90 72 234 198 90 0 234 36 0 18 1,368 Inspecting for Performance (Miterials) 1 I 54 0 18 18 0 0 72 0 0 0 270 0 432 Specialized Technical Training Tottis 107 120 6.237 3.483 6.692 3.946 5.898 1.285 5.404 699 1.524 9.741 8.758 1.501 55.168 Instructional-Hour Data A-4 NUREG-1272, Vol.10, No. 3

APPENDIX B Student Totals by Course l

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CONTENTS Tables Page B-1 Reactor Technology Student Totals by Course ..................................B-1 B-2 Specialized Technical Training Student Totals by Course .........................B-2 Key QTY = Quantity of Courses C-W = Quantity of Course-Weeks IH = Instructional-Hours

1. S = Number of Students R1 = Region I R2 = Region II R3 = Region III R4 = Region IV NRR = Office of Nuclear Reactor Regulation AEOD = Office for Analysis and Evaluation of Operational Data NMSS = Office of Nuclear Material Safety and Safeguards RES = Office of Nuclear Regulatory Research CTR = NRC Contractors IP = International Programs Personnel (Foreign Nationals)

SP = State Programs OTH = Other NRC Offices or Other Agencies TOT = Total 1

1 NUREG-1272, Vol.10, No. 3 B-iii

Technical Training AEOD Annual Report,1996 Table B-1 Reactor Technology Student Totals by Course Rt R2 R3 R4 NRR AEOD NMSS RES IP AS SP OTH TOT COURSE QTY C-W #S #5 #S #S #S #S #S #S #S #S #S #S #S Gezeral Electric Technology GE BWR/4 Technology (R-104B) 1 I 3 1 5 2 1 0 0 0 0 0 0 2 14 GE BWR/4 Technology (R-200B) 1 3 0 0 0 0 6 0 0 0 0 0 0 0 6 GE BWR/4 Technology (R-304B) 2 6 4 0 11 1 10 0 0 0 8 0 3 0 37 GE BWR/4 Advanced Technology 2 4 4 0 8 1 9 0 0 0 8 1 0 0 31 GE BWR/4 Simulatar 6 12 3 1 8 1 9 0 0 0 7 1 1 0 31 GE BWR/4 Simulator Refresher 6 6 13 1 11 3 0 0 0 0 0 0 0 0 28 GE Nuclear Engineering i 2 3 0 0 2 2 1 0 0 0 0 0 0 8 GE BWR/4 Technok Review 2 2 4 4 1 3 2 1 0 0 0 0 0 0 15 Westinghouse Technology Westinghouse Technology (R-104P) 1 I 3 0 5 1 2 0 0 0 1 0 0 1 13 Westinghouse Technology (R-304P) 2 6 3 4 8 8 4 0 0 0 4 1 0 0 32 Westinghouse Advanced Technology 2 4 3 4 8 8 3 0 0 0 4 1 0 0 31 Westinghouse Simulator (R-621P) 2 2 1 0 0 2 3 0 0 0 1 0 0 3 10 Westinghouse Simulator (R-624P) 6 12 2 5 9 8 2 0 0 0 4 0 0 0 30 Westinghouse Simulator Refresher 9 9 10 10 17 5 5 0 0 0 0 0 0 2 49 Westinghouse Nuclear Enginering i 2 0 0 1 1 4 3 0 0 0 0 0 2 11 Westinghouse Maintenance Overview 4 4 9 12 7 8 6 2 0 0 0 0 0 0 44 Westi ouse Technol Review 2 2 3 4 3 0 2 0 0 0 0 0 0 0 12 Combustion Engineering Technology 1 3 2 0 3 1 1 0 0 0 0 0 0 0 7

,CE Cross Training CE Simulator Refresher 4 4 3 4 0 11 4 1 0 0 0 0 0 0 23 Brbcock & Wilcos Technology B&W Cross Training 1 3 1 3 1 2 0 1 0 0 0 0 0 0 8 BaW Simulator Refresher 2 2 1 3 2 0 0 0 0 0 2 0 0 0 8 l

Generic Reactor Technology Reuctor Concepts 3 3 1 0 0 17 3 0 0 1 1 0 0 5 28 P tives on Reactor Safety 1 1 5 0 1 2 6 9 0 0 2 2 0 0 27 Reactor Technology Totals 62 94 81 56 109 87 84 18 0 1 42 6 4 15 503 NUREG-1272 Vol.10,No. 3 B-1 Student Data

AEOD Annual Report,1996 Technical Training Table B-2 Specialized Technical Training Student Totals by Course l

l l l l RI R2 R3 R4 NRR AEODl NMSS! RESl AS IP SPl OT TOT l lCOtJRSE l QTY lC-Wl #Sl #S #Sl #Sl #Sl #Sl #SI #Sl #S #Sl #Sl #Sl #Sl Prsbabilistic Risk Assessment l l l l l l l l l l l l l Probability & Statistics for PRA l 2 2l 4l 3l 3l 3l15l 4l 0l 3l1l 0l 0l ll 37l lPRA Basics for Regulatory Applications l 5l $l12l 4l13l 2l23l ll 2l 2l 21l 0l 0l 3l 83l lPRA Insights into IPEs l $l $l 5l25l32l 3l 14l ll 0l 6l2l 2l 0l O! 90l System Modeling Techniques l 2l 2l 3l 2l 3l 2l10l 4l 0l ll 2l 0l 0l 1l 28l lIRRAS Basics l 2l 2l 4l 2l 2l 2l12l 3l 0l llll 0l O! O! 27l l Advanced IRRAS l 2l 2l 3 2l 2l 2l 7l 3! 0 2l2l 0l 0l O! 23l filuman Reliability Assessment l ll ll ll 3l 2! 3l 2l ll 0l 1l 0l O! 0l ll 14l Risk Assessment in Event Evaulation l 2 2l 3l 7l 2l 1l 10l 2! 0l 1l O! O! O! 0l 26 0 O l l l l l l l l O l l l l O h lEttineering Support l l l l l l l l l l l l l l l Power Plant Engineering l ll 3l ll ll ll O! 6l 0l 0l 1l 0l 0l 0l 3l 13l l Emergency Diesel Generators l 2l 2 13l 1l 12 3l 1 2l 0l O! 0l 0l O! 0l 32l l Motorized Valve Actuators l 1 ll 2 O! 3l O! 2l 0l 0l 0l 0l O! O! 0l 7l l Welding Technology & Codes l 1l 2l 1 0 2l 0l 3l 0l 0l 0l 0l 0 O! 0l 6l Di2 ital 1&C Workshop f 1l 1l 3l ll 2l 2l 6l 4l Ol 1l Ol 0 0 1l 20 0 k l l l ll O f I ll l l 4 1 0 h lRidiation Protection l l l l l l l l l l l l Site AccessTraining l 4l 4l 0 0l 0l 1l 22l 2l 14l 1l 0l 0l O! 4l 44l lSite Access Refresher Training l 8l 8l 31 0l 0l 0l 99l 7l 26l 0l 0l 0l O! O! 163l l Radiation Worker Training l 2l 2l 0 0l 0 O! 0l Ol 9l O! 0l O! O! O! 9l lIn-Place Filter Testing Workshop l 1l ll 0 1l 0l O! 0 Ol 0l 0l 0 0l 0l 0l 1l l Applied IIcalth Physics l 2l10l 0 2 0 0 0l 0l 4l 0l 0 0l 4ll Of 47l l Environmental Monitoring l 1l ll 4 0! Ol 3l Ol 0l l! 0 Ol12l 0l 0 20!

l Introduction to llealth Physics l Il 1l 0 0l O! ll 1l 0l 11l O! 1l ll O! 3l 18l llicalth Physics Engineering ll 1l 0 1l 0l O! 0l 0l Ol Ol 0l 24l O! Ol 25l lRt.d. Surveys in Support of Decomm. l 2l 2l15 0 1l 4l 7l Of 26l 0l 0l 0l 0l 0l 53l j

!}Iealth Physics Technology l 2l 4l 1 1l 6 6l 0l ll O! O! 1l 31l 0l 0 47l l Red. Emergency Response and Oper. l 2l 2l 0 1 0l 2l 0l Of 0 0l 0l 0l 0 0l 3l l Diag. & Thera. Nuclear Medicine l 3! 3! 8 2l 8l 3l 0l 0l 3l 0! 1l 25! 0l 1l 51l l Radiological Accident Assessment l 2l 2! l Of 0l 2l 2l 0l 0 O! 0l 0l 0l 0l 5l lTransportation of Radiologir* Materials  ! 2l 2l 16 0l 9! 2l 0l 0l 3! 1l 0l 14! 16l O! 61l Student Data B-2 NUREG-1272, Vol.10, No. 3

Technical Training AEOD Annual Report,1996 Table B-2 Specialized Technical Training Student Totals by Course l l l lRIlR2lR3 R4 NRR AEODl NMSSlRES! IPl AS SPl OT! TOT l l COURSE l QTY lC-Wl #Sl #Sl #Sl #Sl #5l #Sl #Sl #Sl #Sl #S #Sl #Sl #Sl l Respiratory Protection l 3l 3 1l 0l 3 6l 0 0l 0l 0l 0l 0l 0l 0l 10!

l Internal Dosimetry & Whole Body Counting l 1l ll 23l 0l 6l 1l O! 0l 0l 0l 0l Of O! 0l 30l l Teletherapy & Brachytherapy l 2l 2l 3l 0l 7l O! 0l O! 2l 0l 0l 21l 0l 0l 33l l Safety Aspects of Welllogging l 1 1 0l 0 2 ll 0l Ol 4l 0l 0l 16 0l Ol 23l Health Physics Tomical Review 11 11 64 25 58l50 0 0 8! 0l 0 75 0 2 282 h O ll O l O l O l Il O l Il l 0 ll O Futi Cycle Technology l l l l l l l l l l l l l l l l lNucleer Criticality Safety l 1l ll 0l 0l 2l 0l 0l ll 14l O! O! 0 0l 1l 18!

l Gen. HP Practices for Fuel Cycle Facilities l  !! ll 0l 4! 3l 2l 0l Il 17l O! 0l O! 0l 0l 27l l Fuel Cycle Technology l Il 1l 0l 1l 2! 1l 0l 0l 10! 2l O! O! 0l 0l 16!

Mech. of Sam 31 int & Measurement f If 1l 0 3 2l 3h 1l 0 15l 0l0 0l Of 1l 25 1: h ll ll ll ll ll l ll l l ll \1 ll ll ll ll l

NUREG-1272, Vol.10, No. 3 B-3 Student Data

AEOD Annual Report,1996 Technical Training Table B-2 Specialized Technical Training Student Totals by Course l l l l RI R2 R3 R4 NRR AEODl NMSSlRESl IPl ASl SP! OT TOT l l COURSE l QTY lC.Wl #Sl #Sl #Sl #Sl #Sl #Sl #Sl #Sl #Sl #Sl #Sl #Sl #Sl Stregvards l l l l l l l l l l Safetuards Technoloey Refresher l 1l 111 4 4l 3 3 11 0l 2! ll 0 0 0 0l 28

!I ll i 11 i l 11 l l l l 14 i 11 i 4 ,

lRegilatory Skills l l l l l l l l l l l l l l Fundamentals ofinspection l 1l 1l 3l 1l 6l 3l 11! 2l 8l 0l 0l 0l 0l 4l 38l lNon Power Reactor l 1 ll 2l 1l 1l 1l 0l O! 0l ll 5l 0l 0l ll 12l Examination Techniques l 1l 1l O! 1l 3l 0l 0l 0l 0l O! 2l O! 0l 1l 7l Inspection Procedures l 2l 2l 0l 0 4l 1l ll 0l 2 0l O! 37l 1l $l 51l l Licensing Practices & Procedures l 2l 2! 1l 4 ll 0l O! 0l 7l O! 0l 37l 0l 6l 56l )

l OSHA Introctrination l 3l 3l 3l 1l 6 77l24l 3l 7l 0l 0l O! O! 0l 121l RootCause/ Incident !nvest Workshop l 5l 5l 7l10l18l 7l 5l 2l 11l O! 6l 0l 0l 2l 68l l Human Performance Invest. Workshop l 2l 2 7l 0l 20l 0l 3l Ol 0 O! 0l 0l 0l ll 3ll l Inspecting for Performance l 6l 6l 6l 16l 5l 4l 13l 11l 5I 0l13l 2l 0l 1l 76l Insxctine for Performance (Materials) l 1l 1 3l O! 1l 11 0 0 4 O! 0 O! 15 Of 24 1 Il  ! l l l l 4 4 ) ll ll ll l 11 1 1 l Specialized Technical Training Totals l 107I 120l 258l 130I 256l 208l 311l 55l 21$l 25l 58l 297l 73l 43l 1.929l l

Student Data B-4 NUREG-1272, Vol.10, No. 3 I

setC FORM 338 u.s. NUCLEAR REGULATORY cOMMisslON 1. REPORT NUMBER m' 52 1102. Ao a N y[

CIBLIOGRAPHIC DATA SHEET NUREG-1272

2. TITLE AND SUBTITLE Vol.10 No. 3 Office for Analysis and Evaluation of Operational Data 1996 Annual Report 3 DATE REPORT PUBLISHED December 1997 4 FIN OR GRANT NUMBER

5. AUTHOR (S) 6 TYPE Or REPORT

7. PERIOD COVERED (inctusrve Dates; FY 1996

s. PERFORMINo ORGANIZATION - NAME ANo ADDRESS (if NRC. prowde Dwson, omco or Repon. U 5 Nucdear Regulatory Commrssa, and meeng cadress. # contractor, prowde nome and meeng acuress J Office for Analysis and Evaluation of Operational Data U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001

9. SPONSORING ORGANIZATION . NAME AND ADDRESS (u NRC. type same as saove . scontractor. prowde NRC Dwson. Omco or Recon. U S Nucdear Regulafory Comfrussen, and mahng adeess J Same as in item 8

10. SUPPLEMENTARY NOTES

11. ABSTRACT (200 macs or aess)

This annual report of the U.S. Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data (AEOD) describes activities conducted during 1996. The report is published in three parts. NUREG-1272, Vol.10, No.1, covers powor reactors and presents an overview of the operating experience of the nuclear power industry from the NRC perspective, including comments about trends of some key performance measures. The report also includes the principal findings and issues identified in AEOD studies over the past year and summarizes information from such sources as licensee event reports and reports to the NRC's Operations Center. NUREG-1272, Vol.10, No. 2, covers nuclear materials and presents a review of the events and concerns during 1996 associated with the use of licensed material in nonreactor applications, such as personnel overexposures and medical misadministrations. Both reports also contain a discussion of the incident Investigation Team program and summarize both the incident Investigation Team and Augmented inspection Team reports. Each volume contains a list of the AEOD reports issued from CY 1980 through 1996. NUREG-1272, Vol.10, No. 3, covers technical training and presents the activities of the Technical Training Center in support of the NRC's mission in 1996.

12. KEY WORDS/DESCRIPToRS (Last nords or phrases that we asest = searchers e eceang the report J 13 AVAILABluTY $TATEMI.NT technical training simulator unlimited reactor technology training engineering support training 14 SECURITY CLASSIFICATION probabilistic nsk assessment training radiation protection training (rn,s eages fuel cycle training safeguards training unclassified regulatory skills training Agreement State tra. .ining digital instrumentation and control training trius Repon; GE BWR/4 simulator Westinghouse simulator Com'oustion Engineering simulator unclassified nuclear engineering workstation simulator Lisbon initiative technical assistance 15. NUMBER OF PAGES 16 PRICE NRCfORM335(2 89)

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