ML20199L297

Office for Analysis and Evaluation of Operational DATA.1997 Annual Report (Technical Training)

ML20199L297
Person / Time
Issue date:	11/30/1998
From:	NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
To:
References
NUREG-1272, NUREG-1272-V11-N03, NUREG-1272-V11-N3, NUDOCS 9901270192
Download: ML20199L297 (46)

Text

-

4- r -- - - - - - - -

,2 f a: a tomd@onp = "; 3'272, n . x ANALYSIS land EVALUATIONLof 0PERATIONAL DATA o .

.... or.

I v.:

. ,c,.,

u

+

~4l ~'

, p .GL- -

- p

.. > L,19. 97< ANN. UkbREP. ORT 5 -

3 I V r-9g _

TECH NIC A L TR AlN1,NG _

i

<n.  ; .s, ><

%kk k\%[ /,

' .,s.yj .

y ,

t ,c.,

3 , ,_ . ., .? *

~

wh j ygy m

I" ll l i, $i . .;;, Nl;h I '

,...;h1)d > . _ _

l

~

@ 3:- g $:(-:\

i s,

3

' . > [, .

2.s ")

\ _m.

l '[ '

lf i if . -

A ,y N

h. . . .i ' dj ftd f  ;! M(f L::

,f G @y

.0;p$l:l$

6. - , i a f"

g.

• Is  :>:

l1 l; ,

l:

Yp't: ' ,

4

' 9901270192 981130

.'OR NUREG .M 'N .N. M ME E B.E E'M N ME 1J72 R PDR j :gr  ?

I AVAILABILITY NOTICE l Availability of Reference Materials Cited in NRC Publications I

NRC p;blications in the NUREG series, NRC regu- NRC Public Document Room lations, and Title 10 Energy, of the Code o/ Federal 2121 L Street, N.W., Lower Level Regulations, may be purchased from one of the fol- Washington, DC 20555-0001 lowing sources: < http://www. n rc.g ov/N R C/PD R/pd r 1. htm >

1 -800-397-4209 or locally 202-634-3273

1. The Superintendent of Documents Microfiche of most NRC documents made publicly l 0;Bo 3 0 2 available since January 1981 may be found in the I Washington, DC 20402-9328 Local Public Document Rooms (LPDRs) located in

<http://www. access.gpo. gov /su docs >

the vicinity of nuclear power plants. The locations 202-512 -1800 of the LPDRs may be obtained from the PDR (see previous paragraph) or through:

2. The National Technical Information Service <http://www.nrc. gov /NRC/NUREGS/

Springfield, VA 22161-0002 SR1350/V9/lpdr/html>

<http://www.ntis. gov /ordernow>

41 703 -487-4650 Publicly released documents include, to name a few, NUREG-series reports; Federal Register no-

-I ne NUREG series comprises (1)ir.hnbal and ad. tices; applicant, licensee, and vendor documents ministrative reports, including those prepared for and correspondence; NRC correspondence and internal memoranda; bulletins and information no-international agreements, (2) brochures, (3) pro-ccedings of conferences and workshops, (4) adju. tices; inspection and investigation reports; licens-dications and other issuances of the Commission ee event reports; and Commission papers and the,ri attachments.

and Abmic Safety and Licensing Boards, and (5) books. Documents available from public and special tech-nical libraries include all open literature items, such A single copy of each NRC draft report is available as books, joumal articles, and transactions, Feder-free, to the extent of supply, upon written request al Register notices, Federal and State legislation, as follows: and congressional reports. Such documents as theses, dissertations, foreign reports and transla-Address: Office of the Chief information Officer tions, and non-NRC conference proceedings may Reproduction and Distribution be purchased from their sponsoring organization.

Services Section U. S. Nuclear Regulatory Commission Copies of industry codes and standards used in a Wash.ngton, DC 20555-0001 substantive manner in the NRC regulatory pro':ess E-mail: are maintained at the NRC Library, Two White Flint

<GRW1 @NRC. GOV >

North, 11545 Rockville Pike, Rockville, MD Facsimile: 301- 415- 2289 20852-2738. These standards are available in the library for reference use by the public. Codes and A portion of NRC regulatory and technicalinforma-tion is available at NRC's World Wide Web site; standards are usually copyrighted and may be purchased from the originating organization or, if they are American National Standards, from-

<http://www.ntc. gov >

American National Standards Institute All NRC documents released to the public are avail- 11 West 42nd Street able for inspection or copying for a fee, in paper, New York, NY 10036-8002 microfiche, or, in some cases, diskette, from the <http://www. ansi.org >

Public Document Room (PDR): 212- 642-4900

l l OFFICEiOR. sh".1 df 23 l

l ANALYSIS and -

EVALUATION of

OPERATIONAL DATA -

i l

i i i i

g a _

1997 ANNUAL REPORT .I _j

, TECH NIC AL TR AININ.G . . . . .

! yp ly?):q M%/ :e S

i.  ; .. xy,r#

. A. a ,

) Wl,Mh}.Ill l d ..

)

f$ ll l yng$

i i

3 he l p[g:,vw:p}  :);; -

y j <

fl , s I

(

J w'.?.... y 4

i p.,cin:: .

x y

, f !'

ll

$ r (fjjj 7j

!.' $ M,ig ' :{hyg

M 248AM ' a e a ae e a a e a a a a a 1272 R PDR

AVAILABILITY NOTICE 4 Availabilhy o-l Reference Materials Cited in NRC Publications NRC publications in the Nu rtEG series, NRC regu- NRC Public Document Room ,

lations, and Title 70, Energ/, of the Code of Federa! 2121 L Street, N.W., Lower Level l Regulations, may be purchased from one of the fol- Washington, DC 2055% 0001 l lowing sources: < http://www.ntc.g ov/ N R C/P D R/pd r1. htm > ,

1-800-397-4209 or locally 202-634-3273 l U S. Gov rinti g ce Microfiche of most NRC documents made puolicly RO. Box !!7082 available since January 1981 may be found in the Wash!ngton, DC 2C402-9328 Local Public Document Rooms (LPDRs) located in

<http.//www. access.gpo. gov /su docs > the v,icinity of nuclear power plants. The locations 202-512 -1800 f the LPDRs may be obtained from the PDR (see previous paragraph) or through:

2. The National Technical Information Service <http://www.nrc. gov /NRC/NUREGS/

Springheld, VA 22161-0002 SR1350N9/lpdr/html>

<http://www.ntis. gov /ordernow>

703 -487-4650 Publicly released documents include, to name a few, NUREG-series reports; Federal Register no-The NUREG series comprises (1) technical and ad- tices; applicant, licensee, and vendor documents ministrative reports, including those prepared for ana correspondence; NRC correspondence and international agreements, (2) brochures, (3) pro- internal memoranda; bulletins and information no-ceedings of conferences and workshops, (4) adju- tices; inspection and investigation reports; licens-dications and other issuances of the Commbsion ee event reports; and Commission papers and the,ir attachments.

and Atomic Safety end Ucensing Boards, and (5) books. Documents available from public and special tech-nical Ebraries include all open literature items, such A single copy of each NRC draft report is available as books, journal articles, and transactions, Feder-free, to the extent of supply, upon written request al Register notices, Federal and State legislation, as follows: and congressional reports. Such documents as theses, dissertations, foreign reports and transla-Address: Office of the Chief Information Officer tions, and non-NRC conference proceedings may Reproduction and Distribution be purchased from their sponsoring organization.

Services Section U. S. Nuclear Regulatory Commission Copies of industry codes and standards used in a Washington, DC 20555-0001 substantive manner in the NRC regulatory process E-mail: are maintained at the NRC Ubrary, Two White Flint

<GRW1 @NRC. GOV >

Facsimile: 301 -415-2289 North, 11545 Rockville Pike, Rockville, MD 20852-2738. These sendards are available in the A portion of NRC regulatory and technical informa-library for reference use by the public. Codes and tion is available at NRC's World Wide Web site:

standards are usually copyrighted and may be purchased from the originating organization or, if  ;

< http://www.nrc. gov > Y " ^** "" " " " ' " " * *

• American National Standards institute All NRC documents released to the public are avail- 11 West 42nd Street able for inspection or copying for a fee, in paper, New York, NY 10036-8002 microfiche, or, in some cases, diskette, from the <http://www. ansi.org >

Public Document Room (PDR): 212-642-4900 l I

OFFICE FOR NUREG - 1272 VOL.11, NO. 3 ANALYSIS and EVALUATION of OPERATIONAL DATA l

N

c .

%; I .

2 s%

gf5 =

yb '

1997 ANNUAL REPORT 5:raumeumstancesern

. gg$

.);

1; k:. $- .

-z /

x g

j -

, . ;_.y a k, x gy y J .:

a y-c '

~ -n l

. : ;x w

1  :

%g M yllz 1y l-ly v[' w -

~"

y, M Je x M1 El y;

7 p: 3

g. ,

k

m. i

00' '? "74, .s v #

fl[

j

] f j f iN.

lw j gx ,

8

'O

.L s g- ..V s$

A' tn . . . . .. i[

.. ag

+++++++++++ < ^,a-

, \,.....f U.S. NUCLEAR D g REGULATORY c a ssi Q*

NOVEMBER 1998 T . - - .-

Lies +,a nx..u.  :- w.Ac wGinu.iwu. Gu >> .,M.L.ra E E E E E E E E E E E 4 5 E

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

• Semiannual Report, January - June 1984, AEOD/S405, September 1984 e Semiannual Report, July - December 1984, AEOD/S502, April 1985 e AnnualReport 1985, AEOD/S601, April 1986 e Report to the U.S. Nuclear Regulatory Commission on Analysis and Evaluation of Operational Data 1986, NUREG-1272, AEOD/S701, May 1987 e Report to the U.S. Nuclear Regulatory Commission on Analysis and Evaluation of Operational Data 1987,NUREG-1272, AEOD/S804 Vol. 2, No.1, Power Reactors, October 1988 Vol. 2, No. 2, Nonreactors, October 1988 e Officefor Analysis and Evaluation of Operational Data 1988 Annual Report, NUREG-1272 Vol. 3 No.1, Power Reactors, June 1989 l Vol. 3, No. 2, Nonreactors, June 1989 e Officefor Analysis and Evaluation of Operational Data 1989 Annual Report, NUREG-1272 Vol. 4, No.1, Power Reactors, July 1990 Vol. 4, No. 2, Nonreactors, July 1990

• Officefor 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 Officefor 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  !

l e Officefor 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 l i

e Officefor Analysis and Evaluation of Operational Data 1993 Annual Report, NUREG-1272  ;

Vol. 8, No.1, Power Reactors, November 1994 i Vol. 8, No. 2, Nuclear Materials, May 1995 l e Officefor Analysis and Evaluation of Operational 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 e Officefor Analysis and Evaluation of Operational Data 1996 Annual Report, NUREG-1272 Vol.10, No.1, Power Reactors, December 1997 Vol.10, No. 2, Nuclear Materials, December 1997 Vol.10, No. 3. Technical Training, December 1997

Technical Training i

ABSTRACT The United States (U.S.) Nuclear Regulatory in this annual report, NUREG-1272, Vol. I1, the p Commission's (NRC) Office for Analysis and staff describes activities conducted during FY 1997.

Evaluation of Operational Data (AEOD) has The report is published in three parts. In NUREG-published reports ofits activities since 1984. The 1272, Volume 11, No. 3, covering technical train-i first report covered January through June of 1984, ing, the staff presents the activities of the Technical and the second repon covered July through Decem- Training Center in support of the NRC's mission. In i ber of 1984. After those first two semiannual NUREG-1272, Vol. I 1, No.1, covering power -

repons, AEOD published annual repons ofits reactors, the staff presents an overview of the activities from 1985 through 1993. Beginning with operating experience of the nuclear power industry the repon for 1986, AEOD Annual Repons have from the NRC perspective. In NUREG-1272, Vol.

been published as NUREG-1272. Beginning with 11, No. 2, covering nuclear materials, the staff the report for 1987, NUREG-1272 has been pub- presents a review of the events and concems lished in two pans, No. I covering power reactors associated with the use of licensed material in and No. 2 covering nonreactors (changed to applications other than power reactors. Throughout

" nuclear materials" with the 1993 report). AEOD these reports, whenever information is presented for changed its annual report from a calendar year a calendar year, it is so designated. Fiscal year (CY) to a fiscal year (FY) repon, and added information is designated by the four digits of the part 3 covering technical training, beginning with fiscal year.

the combined Annual Repon for CY 1994 and FY 1995, NUREG-1272, Vol. 9.

iii

Technical Training -

CONTENTS i

! Abstract... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . ..iii

, Abbreviations .. .... . ... . . . . . . . . . . . . . . . ... . . . . . . . . . . . . . . . .. . . vii !

4 Executive Summary... . . . . , . . . . . . . . . .. ... . .. . . ............ix 1 Introduction.. ... . . . . . . . . . . . . . . . . . . . . . . .. . . . _ . . . . . . . . . . . .. .1 i

2 Technical Training Programs . . ... . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . .3 2.1 Reactor Technology Curriculum... . . . . . . . . . . . . . .. . . . . . . .. 3 .

2.2 Engineering Support Curriculum. . .. . . . . . . . . . . . . . .. . . ... ....4 ,

2.3 Probabilistic Risk Assessment Curriculum. . ... . . . . . . . . . . . .. . . .5  !

2.4 Radiation Protection Curriculum . . .... . .. .. .. .. ... .. . . . . . . . .5 2.5 Fuel Cycle Curriculum. . ... . . . . .. .... .... . .. . . . . . . . . . . . . . . .6 2.6 Safeguards Curriculum . ......... .... .. . .. . . . . . . . . . . . . ... .. .. .7 2.7 Regulatory Skills Curriculum ..... . . . . . . . . . . . . . . . . . . . . . .. ......7

' 2.8 Agreement State Training . . ... ... . . ... ... . .. . . . . . .. ... ....8 3 Simulator Projects. . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . ... .. .. . . . .. . 9 3.1 GE BWR/4 Simulator . . . . .. . . . . . . . . . . . . . . . . . . . . . .. .. . . . . . . . . . . . . . . .9 3.2 Westinghouse Simulator . ... . . . .. . . . . . . . . . . . . . . . . ... . . . . . . . . . ..9 3.3 Combustion Engineering Simulator.. . . . . . . . . . . . . . . . . . . . . . . . . .9 3.4 Babcock and Wilcox Simulator . ... . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . .10 3.5 GE BWR/6 Simulator . .. .. .... .... . . . . . . . . . . . . . . . ... . . . . . . .. . . . 10 3.6 Simulator Hardware Maintenance .. . . . .. ... . . . . . . . .. . . . .. . . . . . . . . . . . .. . 10 3.7 Simulator Software Maintenance.... .. . . . .. ... . . . . . . . . . . . . . . . . . . . . . .. .. 10 3.8 Nuclear Engineering Workstation Simulator... . . . . . . . . . . . . .. ...........10 4 Other Technical Training Activities .. .. . .. .. . . . . ... . . .. . . .. . . 13 4.1 Revision ofInspection Manual Chapters 1245 and 1246. . . . . . . . . . . . . . . ... 13 4.2 Technical Assistance to Others... . .. . . . . . .. .. .... .. . . 13 1

4.3 Lisbon Initiative Technical Assistance .. . .. . .. .. . . . . . . . . . . . . . . ... .. . .. .14

4.4 Staff Development .... . .. . .. . . . . . . . . . . . .. . . . . . . .. . . .. . .. .. ... 15 4

i i

! Appendices i

l A Instructional-Hour Totals.... .- . .. .... ... ... .. . . . . . . . . . . . . . . . . . . . . . . . . . . .. .. .A B Student Totals . .... .. . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . .. .B j

4

?

4 i

k i

i V

o i

Technical Training ABBREVIATIONS A H ABET Accreditation Board for Engineering HDR high dose remote afterloading and Technology HICB Instrumentation and Controls Branch ABHP American Board of Health Physics (NRR)

ACRS Advisory Commitee on Reactor Safeguards (NRC) I AEOD Analysis and Evaluation of Operational IIT Incident Investigation Team Data (NRC Office for) IEEE Institute cf Electrical and Electronics AIT Augmented Investigation Team Engineers ANS American Nuclear Society IMC inspection manual chapter ANSI American National Standards Institute I&C instrumentation and control A.PSWG Armor and Protective Systems Working Group J B

^ " ' """YS#8 B&W Babcock and Wilcox Company M BWR boiling-water reactor MEPNS Ministry of Environmental Protection and Nuclear Safety of Ukraine C

MOV motor operated valve CE Combustion Engineering Company CFR Code of Federal Regulations N NDE nondestructive examination D

NEWS nuclear engineering workstation DEC Digital Equipment Corporation simulator DNS domain name service NFS network file system DOE Department of Energy NIS network information system NMSS Nuclear Material Safety and Safeguards E (NRC Office of)

ECT eddy current testing NRA Nuclear Regulatory Authority EDG emergency diesel generator NRC Nuclear Regulatory Commission EOP emergency operating procedures NRR Nuclear Reactor Regulation (NRC EP emergency preparedness Office of)

EPRI Electric Power Research Institute O

F OAS Organization of Agreement States j FY fiscal year OSHA Occupational Safety and Health  ;

Administration G 1 P l' GAN Gosatomnadzor of Russia GE General Electric PIP PRA Implementation Plan P&lD piping and instrumentation diagram PRA probabilistic risk assessment PWR pressurized-water reactor vii

1997 AEOD Annual Report R T RES Nuclear Regulatory Research (NRC TTC Technical Training Center Office of) TfD Technical Training Division RPS reactor protection system RWT NMSS radiation worker training U URTC Ukrainian Radiation Training Center SAT site access training SART site access refresher training SPDS safety parameter display system I

NUREG-1272. Vol. I 1, No. 3 viii

Technical Training EXECUTIVE

SUMMARY

The Office for Analysis and Evaluation of Opera- simulator training (one week of which concentrates tional Data (AEOD) was created in 1979 to provide on emergency operating procedures (EOPs)). This a strong, independent capability to analyze and integrated reactor technology training was con-evaluate operational safety data associated with ducted multiple times throughout the year. Cross activities licensed by the U. S. Nuclear Regulatory training courses, simulator refresher training, and

. Commission (NRC). AEOD is also responsible for a variety of other stand-alone reactor technology the NRC's Incident Response, Incident Investiga- courses were conducted to support NRC staff tion, and Technical Training Programs. The Techni- qualification programs. Reactor technology '

cal Training Division (TfD) of AEOD manages the courses were also attended by foreign and state technical training programs as well as the Technical regulatory personnel, t Training Center (TTC) and associated capital assets.

Upgrades to the reactor technology curriculum The Technical Training Program provides initial included continued incorporation of more perfor-and continuing technical training defined by formal mance-based instructional methods focusing on qualification, development, and training programs improving regulatory skills ofinspectors. Systems for NRC staff and contractors. Technical training courses were revised to add simulator system includes reactor technology programs and special. walkdowns emphasizing the control room controls ized technical programs. Reactor technology and indications for the system being covered.

programs include a spectrum of courses, including Course materials were also revised to incorporate classroom and simulator instruction, in each of the the latest Owners' Group guidance for emergency four Nuclear Steam Supply System vendor designs perating procedures and to reflect current technical

- General Electric, Westinghouse, Combustion and regulatory issues. Considerable development Engineering and Babcock and Wilcox (B&W). finteractive plant system diagrams using the Specialized technical training is provided in engi- Nuclear Engineering Workstation Simulator neering support, probabilistic risk assessment, (NEWS) was completed in GE technology. Practi-radiation protection, fuel cycle technology, safe- c I ci ss exercises for transient analysis and techni-guards, and regulatory skills. c 1 specific tion usage in the advanced technology courses continued to be expanded and improved.

During 1997 TfD presented 60 reactor technology Shutdown operations were expanded in simulator courses and 76 specialized technical training courses in response to current events and agency courses. This training was accomplished in 55,770 interest, use of piping and instrumentation diagrams instructional-hours. An instructional-hour is to analyze plant problems was incorporated, and the defined as I hour of training for 1 student. Most of simulator examination methodology was revised.

this technical training was provided in support of Examination questions cover several different plant qualification programs for NRC technical staff. conditions and focus on safety significance, technical specifications and/or regulatory actions required.

Reactor Technology Training The core of reactor technology training provided in Engineering Support Training support of initial qualification programs for NRC New student manuals have been developed for the staff continues to be an integrated series of courses Nondestmetive Examination (NDE) Technology and consisting of a three-week systems course, a two- Codes course and the Eddy Current Testing (ECT) week advanced course, and two weeks of reactor course. New instmetor guides were developed for the ix

1997 AEOD Annual Report  !

l NDE Technology course, the ECT course, and the Radiation Protection Training Welding and NDE Overview course. New contracts for Motorized Valve Actuators and Emergency The Safety Aspects ofIndustrial Radiography Diesel Generators (EDG) training were awarded in course was presented in Niantic, CT for the first September 1997. Commercial digital instmmentation time. The Transponation of Radioactive Materials and controls course listings were updated with the course materials were revised to incorporate the most recent courses available from the industry. ne most recent transportation rule changes. A new Digital Instrumentation and Controls Work Group contract for Site Access Training (SAT), Site Access held a second Regulatory Perspectives Workshop in Refresher Training (SART), NMSS Radiation February 1997at NRC headquarters with attendance Worker Training (RWT) was awarded. The RWT by 20 people from NRR,1TD, RES, ACRS, Regions course was revised to reflect changes in NRC I,II, III and IV, and AEOD. regulations and Management Directive 10.13, and the SAT manual was updated to include minor revisi ns t the text and the latest edition of 10 CFR Probabilistic Risk Assessment Part 20. A computer based training program, SELF (PRA) Training S ART," was developed by the 'ITD and distributed t the Regions to facilitate the availability of The PRA curriculum continued to expand during refresher trammg. The first presentation of the FY 1997. The PRA for Technical Managers coarse newly developed Emergency Preparedness (EP) was presented for the first time, development of the ,

Technology Course was conducted at the TTC. This Accident Consequence Analysis and External c utse pr vides participants with an understanding Events courses was completed and the courses f EP fundamentals.

presented for the first time, and development of the PRA Technology and Regulatory Perspectives course was completed. The PRA for Technical Fuel Cycle Training Managers course is designed to introduce the NRC technical manager to PRA concepts including Work continued on development of the fuel cycle reactor and non-reactor applications. The Accident technology training curriculum to support NMSS.

Consequence Analysis course deals with Level 3 The curriculum consists of eight courses, seven of analysis, including environmental transport of radio which have been developed in a classroom format.

nuclides and the estimation of offsite consequences Work was initiated to convert the classroom courses from core damage accidents. The External Events to a directed self-study format to make the training course deals with the analysis of extemal events more cost-effective for the small number of staff such as fires,11oods, eanhquakes, high winds, and who will require this training for the future. Conver-transponation accidents. The course provides the sion of the Fire Protection for Fuel Cycle Facilities student with information that can be used in the Course and the General Health Physics Practices review of the results of the individual plant examina- for Fuel Cycle Facilities Course was completed.

tions of external events. The PRA Technology and Conversion of courses will continue during FY Regulatory Perspectives course addresses the special 1998. A new course, General Health Physics needs of Regional Inspectors, Resident Inspectors, Practices For Uranium Recovery, was presented for and other technical personnel who require knowl- the first time. In addition, AEOD obligated funds to edge of PRA issues and insights to better evaluate the complete development of a CD-ROM computerized effects of design, testing, maintenance, and operating training program for the Portsmouth Gaseous j strategies on system reliability.ne course concen- Diffusion Plant.The program will be used to j trates on the application of PRA results in inspection facilitate training of fuel facility inspectors and is planning, monitoring licensee performance, and also expected to be useful for emergency response l

reviewing licensee risk-based submittals. for Ponsmouth.

l l

NUREG-1272, Vol. I 1, No. 3 x

Technical Training Regulatory Skills Training maintenance. Routine preventive and corrective L hardware maintenance is accomplished by contrac-The first presentation of the new Field Techniques tor maintenance technicians while major engineen-and Regulatory Prar.tices course was held in March ing modifications such as simulation computer 1997. The course provides students with the oppor- replacement are accomplishud by 'ITD simulator tunity to apply knowledge and skills learned during engineers.

previous training and cn-the-job experience.

Emphasis is placed on student application of The Safety Parameter Dispi / System (SPDS)

~ important, job-relevant skills and knowledge in software was modified on the GE BWR/4 simulator realistic, interesting scenarios. The Fundamentals of to take advantage of upgraded communications Inspection course chapters on Inspection Reports software associated with the graphics system. I and Enforcement were revised to incorporate A number of Westinghouse simulator control revisions to Inspection Manual Cnapter (IMC) 0610 benchboard recorders and digital indicators were

" Inspection Reports" and the Enforcement Manual.

The Inspection Procedures course was revised t replaced with new devices to improve hardware incorpor2e updated reference material and case- reliability. In addition, work continued on replacing work stua and to reorganize the manual. The the simulation computer systems which are nearing 1.icensing Practices and Procedures course was also the end of their service life.

revised to incorporate updated reference material, Extensive work was performed on the Combustion sample license applications and licenses and a new Engineering simulator Reactor Protection System expanded licensing overview presentation. (RPS) hardware to improve performance and

, reliability. Several process controllers as well as a Agreement State Training numba of remdes and metus wee mplaced.

Computer system hardware and software support FY 1997 was the first year in which the Agree- was obtained for the Silicon Graphics computer ment States were required to pay for NRC spon- systems that serve as the simulator computer sored training. Pending review of the impact of platforms.

this new policy on the Agreement States, registra-tion fees were waived for all contracted courses. The project to procure and install replacement Except for a select few state Radiation Control coinputer systems for the Babcock and Wilcox Agencies who were u: able to make budgetary simulator was completed in FY 1997. Simulator arrangeroents, all states were required to pay for reliabRity has been improved since completion of their own tinel and per diem. Fifty-seven percent this Pr ject A C ntract was Put in P ace l to provide of the students et the six major nu&ar materials advanced software programming and model devel-courso presented in FY 1997 represented Agree- pment tools. These tools will be used to begin ment States (or states which are becoming Agree-e pment of newa mWels for the B&W simula-I 'I impr ve fidelity of performance and add ment States). One five-week Applied Health .

Physics course was conducted in Oak Ridge TN additional functionality.

with the majority of attendees being from the Work continued on replacement of the Aydin Agreement States. The NRC/OAS (Organization display systems for the B&W and BWR/4 simula-of Agreement States) Training Working Group, tors. These systems provide control board graphi-comprised of members from NMSS, OSP, AEOD cal displays of systems and process parameters and three Agreement States, conducted several from the process computers. A bilateral agreemer,t meetings in FY 1997 and drafted a fmal report.

was put in place with the Halden Reactor Project which provided development support for the Simulation Activities Pmjects. Completion of these projects will allow retirement of the 20 year old computers that are Simulator reliability and availability are achieved currently used for the process computers.

through a program of preventive and corrective xi Executive Summary

1997 AEOD Annual Report Other Technical Training Activities have assisted the respective regulatory agencies in the establishment of comprehensive systems for Revision of Inspection Manual Chapters training and quahfication of technical personnel of -

1245 and 1246 the Ministry of Environmental Protection and j Nuclear Safety (MEPNS) of Ukraine and the  ;

NRR issued an extensive revision to IMC 1245 in l December 1996. This revision reflects current NRR Gosatomnadzor (GAN) of Russia. The last fonnal  ;

activity under Pnonty 5 is planned for October policy on training requirements for inspectors.

1997. Both pnonties are planned for closure m -

PWR inspector classifications were redefined to

• ^'I W U. . Future co-operation withm the specify renuisements for each of the three PWR . Y. .

vendor lines. Additionally, three new inspector Pnonties will be maintained in the form of TTD c nsultations regarding the training progrants and slassifications: Reactor Technical Specialist / Team c urses developed by MEPNS and GAN.  ;

i Member, Reactor Emergency Preparedness or Health Physics Specialist / Team Member and Under the framework of Russian Pric tity 5.1, the  !

Reactor Decommissioning Inspector were added. NRC has provided two Analytical Simulators to Addi:lonal refresher training requirements were Russia for training of regulatory personnel and

! added in several parts, the Root Cause/ Incident under the framework of Ukraine Priority 2.1, NRC l Investigation Workshop is required for all inspec- has provided one Analytical Simulator to the >

tors and the Reactor Safety course is required for Ukraine for training of regulatory persornel. TTD

! most inspectors. also supported a DOE-sponsored visit by eighteen representmives fr m nucle r generating plants and Lisbon Initiative Technical Assistance regulatory agencies in Russia, Ukrame, Hungary, TTD continued to be actively involved in technical Slovakia, Bulgaria, Hungary, and the Czech Repub-assistance to Russia and Ukraine under the Lisbon lie at the Technical Training Center in November Initiative. Ukrainian Priority 2 and Russian Priority 1996 to leam about pressurized water reactor 5, Establishment of Regulatory Training Programs, emergency operating procedures.

t i

! i 2

4 l NUREG-1272, Vol. I 1. No. 3 xii L i

Technical Training 1 INTRODUCTION AEOD provides technical training for NRC person- regulatory skills. Specialized technical training is nel to satisfy integrated training needs defined by provided through customized courses developed by formal NRC staff qualification and training pro- the staff, customized couises by contractors, grams. New courses are developed and existing coordination of slots (training opportunities) in courses are modified to meet new or changing courses that are presented by other Government requirements identified by headquaners and re- agencies, and the identification and promotion of gional offices. Principles of the systems approach to apprcpriate commercially available courses that training are routinely used throughout the life cycle NRC personnel may attend as individual training of the technical training courses, opportunities. For many of the contracted courses,

.. . NRC perspectives are provided by designated Techm.cr.1 trammg includes reactor technology individuals from within the NRC staff.

programs and specialized techmcal programs.

Reactor technology training courses are imple- The Technical Training Division (TTD) of AEOD mented, maintained, and improved in each of the manages the Technical Training Center (TTC) and four reactor vendor designs - General Electric (GE), associated capital assets in Chattanooga, Tennessee, Westinghouse, Combustion Engineering (CE), and where most of the reactor technology training is Babcock and Wilcox (B&W). The curriculum conducted. Reactor technology courses are typically includes a spectnam of courses involving both presented by TTD staff. Each of the full-scope classroom and simulator training, reactor simulators and associated computer equip-

. ment is operated, maintained, and upgraded by TTD Speciah. zed techm. cal training courses are imple-staff. TTD staff also provide technical assistance in mented, maintained, and improved in engineering areas of expertise to other NRC offices as well as to support, probabilistic risk assessment, radiation foreign regulatory counterparts.

protection, fuel cycle technology, safeguards, and I

Technical Training 2 TECHNICAL TRAINING PROGRAMS During FY 1997, the TTD provided a total of 60 2.1 Reactor Technology Curriculum courses in the reactor technology areas and 76 more in the specialized technical training areas. These The core of reactor technology training provided in courses represent a total of 175 course-weeks,90 of suppon of initial qualification programs for NRC i which were associated with reactor technology staff continues to be an integrated senes of courses training and 85 of which were associated with consisting of a three-week systems course, a two-specialized technical training. Course-weeks can week advanced course, and two weeks of reactor typically be correlated to TTD staff effort or simulator training (one week of which concentrates contractor dollars required to conduct training. All on emergency operating procedures (EOPs)). This courses falling under the TfD program element and integrated reactor technology training was con-listed in the TTD Course Catalog are included in ducted multiple times throughout the year. Cross these totals. This quantity of training resulted in training courses, simulator refresher training, and a 55,770 instructional-hours of which 24,71I were variety of other stand-alone reactor technology associated with reactor technology training and courses have been conducted to support NRC staff 31,059 with specialized technical training. Most of qualification programs. Reactor technology course this technical training was provided in support of students included a significant number of foreign qualification and development programs for NRC and state regulatory personnel.

technical staff.

Major curriculum development areas during FY l An instructional-hour is dermed as I hour of 1997 included revsion of course materials to l training for 1 student devoted to any of the follow- incorporate latest Owners' Group guidance for

! ing activities: lectures, seminars, discussions, emergency operating procedures. Significant problem solving sessions, quizzes, examinations, progress was made for the Combustion Engineering on-the-job training, laboratory exercises, pro- pressurized-water reactor (PWR) and the GE grammed leaming, and simulation exercises. For boiling-water reactor (BWR)/4 technologies. This is 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 10 students an ongoing effort which will continue into FY l would constitute a total of 160 instmetional-hours. 1998. Other curriculum development during FY n ng ng upgrade, enhancene, and Table A-1 shows the annual reactor technology

< . maintenance of course materials m all technologies instructional-hour totals by course group. Table A-l to reflect current technical and regulatory issues.

2 shows the annual reactor technology instruc-

, Considerable development ofinteractive plant tional-hour totals by course for the various reactor technology areas. Table A-3 shows the annuai "I'I#* agrams using the Nuc.iear Engineering Workstation Simulator (NEWS) was completed in specialized techm. cal training instructionai-hour GE technology. These interactive system diagrams

! totals by course for the various specialized areas.

ar us d to enhance student understanding of For some comparisons, it is more usefui to view sys em amms and intedaces.

statistics based on numbers of students rather than

numbers of instructional-hours. Table B-1 shows Revision of Westinghouse course materials to a

the annual reactor technology student totals by suppon the incorporation of the Troju simulator course for the various reactor technology areas. into the Westinghouse curriculum continued.

Table B-2 shows the annual specialized technical Advanced course manual chapters, lesson plans, 1 training student totals by course for the various graphic illustrations, exam bank questions and j specialized areas. Trojan-based Technical Specifications were J

1 3

i, .

AEOD Annual Report,1997 i

l completed. Development of additional simulator significance, technical specifications and/or i test and operating procedures, scenarios, and regulatory actions required.

instructor lesson plans to support simulator courses was completed. Cross training courses in Combustion Engineering and Babcock and Wilcox technologies were pre-Upgrades continued to the full course series to sented. Upon course completion, the students were incorporate more performance-based instructional surveyed to obtain their insights regarding the j methods focusing on improving regulatory skills of content and level of course presentations. Student i inspectors, and to tie the courses together more feedback is one of the elements in the continuing closely. The changes for the systems course in- effon to ensure that technical training courses volved adding simulator system walkdowns empha- address user needs. One result of this feedback will sizing the control room controls and indications for be the inclusion of additional plant transient infor-the system covered. The intent of the changes was mation into future courses.

l to reinforce the theoretical system description, purpose, and design covered in the classroom, with practical visual and mechamcal reviews of the 2.2 Engineering Support Curriculum lecture material in the simulator. Another change in New student manuals have been developed for the the systems course was the elimination of the Nondestructive Examination (NDE) Technology graded mid-course quiz, and implementation of and Codes course and the Eddy Current Testing several stmetured, but ungraded short written (ECT) course. New instructor guides were devel-practice quizzes. This provides several, more oped for these courses and the Welding and NDE focused reviews in a less threatening setting. Overview course. These courses assist NRC techni-

. . cal managers and other technical personnel in Practical class exercises for transient analysis and .

' techm. cal specification usage in the advanced developing a general familiarity with metallurgy, welding, and nondestructive examination technolo-technology courses continued to be expanded and improved. A risk management module was devel-gies, including welding fabrication, welding oped and a.lded to the techm.calissues section of processes, welding inspection, ultrasonic testing, the advanced technology courses. Th.is module is radiographic testing, eddy current testing, l.iquid penetrant testing, and magnetic particle testing.

provided in the reactor technology full course series to give students insights and discussions regarding Current commercially available courses were made PRA use by licensees and the NRC in managing available to support staff training in the area of and assessing risk at the plants. digital instmmentation and controls. Course topics include instmmentation and control fundamentals, In the simulator courses, the schedule was revised process controls, industrial measurement and control, from two 1-week courses to one 2-week course.

microprocessor fundamentals, software engineering, This gives more flexibility to ensure adequate time software verification and validation, and program-I for higher priority conditions / scenarios. Shutdown mable controllers. These courses are available to the l operations were expanded in simulator courses in staff as individual training opportunities through the response to current events and agency interest. Use l NRC Form 368 process and are held by selected

of piping and instrumentation diagrams to analyze commercial firms such as the Instrumentation

! plant problems was incorporated into the simulator Society of America and General Physics.

courses. Use of Emegency Action Levels and Event Classification Guides was incorporated into New contracts for technical assistance in Motorized the simulator courses. In addition, the simulator Valve Actuators and Emergency Diesel Generators examination methodology was revised to incorpo- (EDG) training were awarded in September 1997.

rate two, more performance-oriented examinations Student manuals will be updated for both courses as into the course, rather than the ene final static pn of these contracts with recent information in exam. Examination questions cover several the regulation of EDG and motor operated valves different plant conditions and focus on safety (MOV) activities at nuclear facilities. The MOV NUREG-1272, Vol.11, No.3 4

Technical Training i T

course will continue to be held at the Indiana The FR A for Technical Managers course is de-Learning Center in Homer City, PA. The EDG tigned to introduce the NRC technical manager to course will utilize the Diesel Generator Laboratory PRA concepts including reactor and non-reactor at the Maine Maritime Academy in Castile, Maine. applications. The course includes an introduction to The laboratory facilities at the Maine Maritime PRA methods used in system modeling, accident Academy are fully equipped with diesel engines of progression analysis, accident consequence analy-both two and four stroke design as well as a com- sis, and performance assessment. In addition to puter assisted diesel simulator and the training ship furnishing a good understanding of the mechanics i State of Maine for in-depth, hands-on exercises. of a PRA, the course provides information on the '

These courses assist NRC technical managers and more detailed training available to the technical other technical personnel in developing a general staff, the current agency policy on the use of PRA, familiarity with MOV and EDG technologies, information on how the agency I as used PRA in including operation and maintenance aspects as making decisions, and the valuc if and methods for  :

well as hands or laboratory sessions which rein- using PRA to get the most ben . from available l force lectures on MOV and EDG resources. Also included is a, assion of PRA I strengths, limitations, uncertan:ry, and agency '

The Digital Instrumentation and Controls Work applications of PRA methodology.

Group held a second Regulatory Perspectives Workshop in February 1997 at NRC headquarters The Accident Consequence Analysis course deals with attendance by 20 people from NRR, TTD, with the portion of PRA typically referred to as RES, ACRS, Regions I, II, III and IV, and AEOD. Level 3 analysis. The course addresses environmen- i This workshop is a cooperative effort with NRR, tal transport of radio nuclides and the estimation of '

the regions and TfD. The workshop gave inspec- offsite consequences from core damage accidents.

tors, reviewers, and project engineers a better The emphasis of the course is on important model-understanding of the digital upgrade process and ing issues and how they are dealt with, rather than addressed methods for conduct of an effective how to use specific modeling software.

inspection of digital instmmentation and control . .

systems using the newly revised Standard Review The External Events course deals with the analysis Plan Chapter 7 on Instrumentation and Control, f extemal events such as fires, floods, earthquakes, and lessons learned 60m recent NRR/HICB high wmds, and transponation accidents. The reviews in Digital! Software, as well as current e urse has been developed to provide the student technical issues sud as radio frequency interfer- with information that can be used in the review of ence and electrrre gnetic interference. The the results of the individual plant examinations of workshcp a pimud as an annual event which will extemal events.

allow for interaction and dissemination of techni- The PRA Technology and Regulatory Perspectives cal information regarding the digital I&C issues course addresses the special needs of Regional facing the agency. Inspectors, Resident Inspectors, and other technical personnel who require knowledge of PRA issues 2.3 Probabilistic Risk Assessment and insights to better evaluate the effects of design, testing, maintenance, and operating strategies on (PRA) Curriculum system reliability. The course will concentrate on The PRA curriculum continued to expand during the application of PRA results in inspection plan-FY 1997. The PRA for Technical Managers course ning, monitoring licensee performance, and review-was presented for the first time, development of the ing licensee risk-based submi'tals.

Accident Consequence Analysis and External Events courses was completed and the courses 2.4 Radiation Protection Curriculum presented for the first time and development of the PRA Technology and 'tegulatory Perspectives In anticipation of the reduced demand for training l

! course was completed, from the Agreement States, only one of each t

l l 5 Training Programs

_~

AEOD Annual Report,1997 contracted course typically shared by NRC and was booked to capacity with attendees evenly Agreement State personnel was scheduled for distributed between NRC and Agreement State )

FY 1997 except where specific demand warranted regulatory personnel, additional presentations. Multiple presentations The first presentation of the newly developed of in-house courses were scheduled as in Emnency Preparedness (EP) Technology Course previous years' was conducted at the 'ITC. NRR requested the The first presentation of the Safety Aspects of course be developed to assist emergency planning Industrial Radiography course was presented in inspectors in their inspection and regulatory over-Niantic, CT under a new contract. The course sight responsibilities. The cumse was developed presentation included a new contractor developed and presented by individuals from NRR, AEOD/ l course manual. Course attendees included represen- IRD ar.d TTD, This course provides participants tatives of Agreement States as well as NRC person- with an understanding of EP fundamentals. Topics l nel. Course materials for the Transponation of covered in the course include: the history of EP Radioactive Materials course were revised to incor- requirements; EP criteria ard guidance documents; porate the most recent transportation rule changes. basic plant systems imponant to safety; severe accidents; license emergency preparedness plans; The Site Access Tra. .mmg (SAT), Site Access prorective action recommendations; drills and Refresher Trammg (S ART), and NMSS Radiation exercises; the EP inspection program; offsite Worker Tram,mg (RWT) courses continue to be emergency planning and NRC interface with the routinely presented at headquarters under a new Federal Emergency Management Agency.

delivery order contract. A contractor provided SART course was also conducted in Region I at their request. At the request of NRR, a TTD staff 2.5 Fuel Cycle Curriculum member conducted a special SAT course at the Brookhaven National Laboratory for NRC contract Work continued on a major new training initiative personnel to facilitate access of these contract in the area of fuel cycle technology requested by the  ;

personnel to licensee facilities. The RWT course Duision of Fuel Cycle Safety and Safeguards was revised in FY 1997 to reflect changes in NRC witDin NMSS. NRC staff targeted for this training regulations and Management Directive 10.131. It include fuel facility inspectors, license reviewers, was presented twice in headquarters. The SAT headquarters staff, and ether personnel who have manual was updated to include minor revisions to regulatory oversight of fuel cycle facilities. Seven the text and the latest edition of Pan 20 of Title 10 f the eight courses in the curriculum have been of the Code of Federal Regulations. Copies of developed in a classroom format.

the manual were provided to all Regional Offices NMSS supported work on the Management Sys-and Headquarters. tems and Structures for Regulators course contin-A computer based training program, "SELF SART," ued by the Office of Human Resources. A new, was developed by the TTD and distributed to the rel ted course, General Health Physics Practices Regions to facilitate the availability of refresher For Uranium Recovery, was developed at the training. This program was developed using request of the Division of Waste Management. The l authoring software procured by tFe TFD. Many of first presentation was held February 1997. Although j the graphics used in the program were obtained n t required in Inspection Manual Chapter (IMC) I from the Internet websites of other Federal Agen- 1246, thk course is intended for urmium recovery cies. The program structure is based on the SAT insp ct rs av.! license reviewern The course Manual and incorporates review questions at the pr vides a fundamental unders anding of health completion of each section. physics for uranium recovery f acilities. Health physics practices and issues fcr uranium mining, The Health Physics Technology Course v,as revised milling, and in situ leach extraction type facilities and updated during FY 1997. Although two courses are discussed. Topics include: brief review of were scheduled for FY 1997, one was canceled radiation units and terminology; naturally occurring due to insufficier., enrollment. The other course radioactive decay chains; special propert;es and NUREG-1272, Vol.11, No.3 6

i Technical Training hazards of uranium and its decay products; general other government agencies to provide training for facility descriptions; radiation issues and hazards security and safeguards personnel.

involving radon-222 releases and windblown tail-ings; radiation dose limits, including the weekly limit for soluble uranium; working level concept for radon u a m M s G m.ulum decay products; contamination control; external dose The first presentation of the new Field Techniques controls; and internal dose controls, including and Regulatory Processes course was held in bioassay and air sampling programs. The approach March 1997. Development of the course was will be to provide a familiarity with the above requested by NRR to support the resident inspec-technica! topics and issues at a fundamental level. tor development program and was subsequently Work was initiated during FY 1997 to convert the m de part of IMC 1245. Presented using a work-previously developed classroom courses to a shop / case study approach, it bridges the gap directed self-study format. The need for classroom between formal classroom training and real-world presentation of these courses peaked in FY 1996. n-the-job performance, emphasizing student The currently projected student needs for these application of important, job-relevant skills and courses no longer supported formal course presen-knowledge in realistic case study scenarios. The tations. However, the viability of the courses had to e urse provides an miroduction and review of the NRC reactor inspector's job, including the prin-be maintained to support new agency hiring and future work associated with NRC regulation of ciples fg d regulation; identification of sigmfi-additional DOE facilities. The directed self-study cant plant pmfenu or issues effecting operability r abih.ty; identifying regulatory basis; devel-format provides a cost-effective mechanism to ping acti n plans t address the issues or prob-maintain availability of the training for a small student population. "* P.ri ritizirg follow-up action plan steps; determimng if the licensee has met notification Conversion of the Fire Protection for Fuel Cycle requirements and taken appropriate shon term and Facilities Course and the General Health Physics immediate corrective actions, and justifying the Practices for Fuel Cycle Facilities Course was analysis; developing recommendations on applica-essentially completed. The remaining courses (with tion of enforcement policy; evaluating the effec-the exception of the Hazards Analysis for DOE tiveness of bcensee corrective actions and quality Safety Ar:alysis Reports (SARs) and Qualitative assuraace practices; communicating findings to Risk Assessment course, and the Management the licensee and regional management; drafting a Systems and Structures For Regulators course) will performance assessment input for SALP, PPR or be convened to self-study format during FY 1998. IPAP that conforms to NRC Inspection Manual Chapter 0610; and demonstrating the application i Funds were obligated to complete development of a of routine inspection procedures.

CD-ROM computerized training program for the Portsmouth Gaseous Diffusion Plant. The program The Fundamentals of Inspection course was held in consists of drawings, photographs, and SAR text Region III in November 1996 and NRC headquaners for the plant and, when completed, would bc used in April 1997. The chapters on Inspection Reports to facilitate training of fuel facility inspectors and and Enforcement were revised to incorporate revi-may be useful in emergency response for Pons. sions to IMC 0610 " Inspection Repons" and the mouth. The work is expected to be completed Enforcement Manual. Future manual revisions will during FY 1998. include new information on risk-informed regulation and performance-based inspections.

2.6 Safeguards Curriculum The Inspection Procedures course was revised in FY 1997 to incorporate updated reference material A Safeguards Technology Refresher course was and casework studies and to organize the manual presented in September 1997. A Bomb Threat into 11 chapters with a more standardized format Recognition Course was presented in September between chapters. The Licensing Practices and 1997 'ITD staff continues to work closely with Precedures course was also revised in FY 1997 to 7 Training Programs

1997 AEOD Annual Report incorporate updated reference material, sample Deliberations of the NRC/OAS (Organization of license applications and licenses and a new ex- Agreement States)Trr.ining Working Group contin-panded licensing overview presentation. One course ued.The working group, comprised of members was presented in Region I to accommodate a from NMSS, OSP, AEOD and three Agreement relatively large number of Regional personnel States, conducted several meetings in FY 1997 and requiring the training. drafted its final report which is expected to be released at the October 1997 All Agreement State

.. Meeting. This working group had been established 2.8 Agreement State Traimng to accomplish the following:

FY 1997 was the first year in which the Agreement a. Evaluate the proposed training courses and States were required to pay for their own tra:ning. training subject areas for the Agreement State Pending review of the impact of this new policy on staff that are necessary to assure equivalency the Agreement States, registration fees were waived with NRC requirements and forward a recom-for all contracted courses. Except for a select few mendation to the OAS and the NRC; state Radiation Control Agencies who were unable to make budgetary arrangements, all states were b. Evaluate the NRC policy for passing /failing required to pay for their own travel and per diem. c urses and determine an acceptable policy and methods to implement a policy for the Agree-Per SECY-97-183, state attendees 'vho offer to pay ment States; and tuition costs or have justified a need for NRC .

funding support are given equal consideration with c. {dentify acceptable alternative training options, including the evaluation of technology and NRC attendees for slots in NRC sponsored courses.

training methods that could be used to lower the

-All others are registered as " space available,,

C st f training courses.

During six major materials courses presented in FY 1997, one hundxd twenty-nine students received Gne five-week Applied Health Physics course was training. Of those, fifty-seven percent represented conducted in Oak Ridge TN with the majority of Agreement States (or states which are becoming attendees being from the Agreement States.

Agreement States).

I l

i I

NUREG-1272, Vol.11 No. 3 8

Technical Training 3 SIMULATOR PROJECTS The Technical Training Division is responsible for 3.2 Westinghouse Simulator the operation and maintenance of NRC full-scope simulators which are an integral part of training A number of control benchboard recorders and digital programs for initial and continuing qualification of indicators were replaced with new devices. These Agency technical staff. The programrnatic goal is steps were taken to improve hardware reliability, to ensure that the simulators are reliable and Work continued on replacing the simulation com-available for scheduled training and possess the puter systems. The original systems are Encore 32/

requisite capability and fidelity to support training 9780s which are nearing the end of their service program requirements. life. The replacement systems will be Encore RSX Simulator reliability and availability are achieved c mPuters with an attached DEC Alpha AXP system. The architecture is similar to that used on through a program of preventive and corrective the BWR/4 simulator.

maintenance, including replacement of obsolete hardware and simulation computers. Routine Work on the computer system replacement has been

preventive and corrective hardware maintenance is slowed by difficulties encountered in a critical path I

accomplished by contractor maintenance techni- corollary project, which is the replacement of the cians while major engineering modifications such Sun 3-based instructor station. The present instruc-as simulation computer replacement are accom- tor system utilizes three obsolete Sun 3 systems and plished by 'ITD simulator engineers. Obsolete (non. which communicate with the present Encore 32/

failed) hardware is rep' aced only if its continued 9780s by means of a shared memory scheme that is service is expected to result in reliability problems not supported on the new RSX computers. The which would impact training. Simulation computers replacement system will reside on the DEC Alpha.

are generally replaced when they have reached the This portion of the project is nearing completion.

end of their service life and are no longer supported by the manufacturer.

3.3 Combustion Engineering Simulation software modifications are developed Simulator l and implemented to address identified deficiencies or modeling improvements required to support Extensive work was performed on the Reactor programmatic needs. All software modifications are Protection System (RPS) hardware to improve accomplished by TTD simulator engineers. performance and reliability of this stimulated system. A sufficient RPS spare parts inventory was obtained, thus improving the ability to maintain I l 3.1 GE BWR/4 Simulator the equipment.

. The Safety Parameter Display System (SPDS) Several process controllers as well as a number of software was modified as necessary to take advan- recorders and meters were replaced with new l tage of the features of the upgraded communica- devices to improve reliability and capability. The tions software received as part of new releases of original controllers were simulated - the hardware the Picasso graphics system. The modification consisted of the controller case, pushbuttons, and reduced the number of open data cormections meters, with computer software simulating the I

required between the simulation computer host controller functions. The new controllers are systems and the Silicon Graphics Picasso server, fully functional, programmable devices. Installa-

. which results in simplification of the process and tion required substantial modification to the improved reliability, simulator software.

9

AEOD Annual Report,1997 Computer system hardware and software support parameters. The update involves replacement was obtained for the Silicon Graphics computer hardware and use of the Picasso graphic system systems that serve as the simulator computer utilized in the nuclear engineering workstations platrorms.This will provide fast tumaround repairs (NEWS). A bilateral agreement was put in place for computer hardware failures and continuing with the Halden Reactor Project which provided operating system software updates and bug fixes development support for the project. Completion if for the simulation computer. The outcome will be this project will allow retirement of the 20 year old improved simulator availability and reliability computer that is currently used for the process for training. computer and modification and improvement of displayed graphics to provide more efficient and 3.4 Babcock &Wilcox Simulator *ff*I"* *' i"i"8' The project to procure and install replacement 3.6 Simulator Hardware computer systems was completed in FY 1997.The replacement system consists of two Encore RSX Ma.mtenance computer systems, with an attached DEC Alpha There were no significant hardware failures during AXP. This is similar in architecture to the system FY 1997.

currently used on the BWR/4 simulator, and to the one being installed on the Westinghouse simulator. A contract is in place for simulator hardware The software timing problems previously observed maintenance. Use of a contractor for these services have been resolved as a result of the computer has greatly reduced TTD simulator engineer replacement producing improved reliability for involvement in routine hardware maintenance, training. allowing more time for simulator engineers to address simulation engineering projects.

Work continued on the project to replace the Aydin display system which provides the control board graphical displays of systems and process param- 3.7 Simulator Software Maintenance eters from the process computer . The update This function is performed in-house using staff involves replacement hardware and use of the

, simulator engineers. TTD simulator engineers made Picasso graphic system utilized m the nuclear software changes as required in support of discrep-engineering workstations (NEWS). A bilateral ancy resolution and change requests. The engineers agreement was put in place with the Halden Reactor also researched the modeling software as necessary Project which provided development support for the to assist the instructional staffin resolving design project. Completion if this project will allow and performance questions.

retirement of the 20 year old computer that is currently used for the process computer.

3.8 Nuclear Engineering Workstation A contract was put in place to provide advanced S,mdator software programming and model development tools. These tools will be used to begin develop- Development of the Nuclear Engineering Worksta-ment of newer models for the B&W simulator t tion Simulator (NEWS) continued during FY 1997.

improve fidelity of performance and add additional Graphical display development for the different functionaFty. Delivery of the software is scheduled technologies continued to be performed primarily for early 1998. by the Reactor Technology Instructors who are members of the NEWS Work Group. The rate of 3.5 GE BWR/6 Simulator picture development is dependent upon the instruc-tors' work schedule and teaching load, the complex-Work continued on the proje to replace the ity of each picture, and the instructor's familiarity Aydin display system which provides the control with Picasso. Because of the teaching and course board graphical displays of systems and process development load, only a limited number of new NUREG-1272, Vol.11, No.3 10

Technical Training displays were developed during the year for the communications software received as part of new PWR technologies. However, development of releases of the Picasso graphics system.

displays for the BWW4 continued.

Because on.. higher priority software development Sufficient Sun Ultra workstations were procured to activities, work on the CE and BWW4 Simulator equip each simulator control room and each class- NEWS connections has been delayed. Completion room with NEWS workstations. This will improve cf & CE siraulator connection is scheduled for the efficiency and effectiveness of training by early 1998. The BWW4 simulator connection will having consistent NEWS information available in then be developed using the software developed for classrooms and simulators. the commumcation between the BWW4 simulator computer and the new SPDS as the basis, signifi-The NEWS software was modified as necessary to cant!y 'hortening development time.

take advantage of the features of the upgraded i

I 1

5 I1 Simulator Projects

Technical Training 4 OTHER TECHNICAL TRAINING ACTIVITIES 4.1 Revision ofInspection Manual the Operator Licensing Branch of NRR, TfD inst Ct rs Pl ayed the role of license candidates,.

Chapters 1245 and 1246 provided assistance in establishing the exam NRR issued an extensive revision to NRC IMC scenarios, and validated the simulator scenarios of 1245 in December 1996. Earlier, NMSS had the examiners-in-training during examination completed an extensive revision to IMC 1246 in techniques courses. TTD staff also provided techni-June 1996. IMC 1245 had historically addressed the cal assistance in radiation protection to a number of qualification requirements of all inspectors, re- regions, NMSS and the United States Air Force.

gional and headquaners, NRR, and NMSS. Its last Other examples of technical assistance provided are major revision was in 1991. IMC 1246 was estab-described below:

lished in 1994 to define qualification requirements for Materials icense Reviewers. Each program .

Staff conducted a training evaluation for AEOD/

office now has direct control over their qualification IRD. The evaluation provided IRD with a matrix programs. The revisions also place the manual of courses in the incident response curriculum chapters in line with regional organizations. and recommendations on course improvements, l resource management and tracking of atten-IMC 1245 was revised to reflect current NRR dance.

policy on training requirements for inspectors.

PWR inspector classifications were renamed to -

Staff panicipated in the Region I Salem Restart specifically recognize each of the three PWR Assessment Team Inspection and TMI emer-vendor lines and three new classifications: Reactor gency preparedness inspection team and assisted Technical Specialist / Team Member, Reactor Region III on the Zion Augmented Inspection Emergency Preparedness or Health Physics Special- Team (AIT).

istfream Member and Reactor Decommissioning .

a Staff participated m. the Arkansas-Region IV Inspector were added. Additional refreshei training Workshop making a presentation on NRC requirements were added in several parts. The Root Incident Investigation Team and AIT inspection Cause/ Incident Investigation Workshop is required for all inspectors and the Reactor Safety course is Fmcesses.

required for most inspectors. .

Staff assisted OSP in drafting a Commission Paper entitled " Guidelines for Providing Assis-

'^"C" t Agreement States and Altematim for 4.2 Technical Assistance to Others Tramm.g.

The TTD staff provided requested technical assis- -

Staff assisted the Office of Human Resources in tance to other organizations consistent with NRC the development of the requirements for, and and TTD priorities, budget and workload consider- evaluation of, a Human Rc:murces Information ations. 'ITD staff possess a spectmm of knowledge, System commercial off-the-shdf acquisitica.

skills and abihties and work experience which allow them to be valaable contributors to a wide +

Staf f provided assistance to RES it; the develop-range of projects. Participation in regulatory ment of three new covses for RES staff on projects not only benefits the sponsoring organiza- Radiation Health Risk Assessment. Regulatory tion, but maintains and improves the regulatory Analysis, and Compliance with the National skills and knowledge of the TTD staff. Technical Environmental Policy Act il NF.C Rulemaking assistance was provided by 'ITD staff in a number and Licensing.

of diverse areas throughout the year. In support of 13

AEOD Annual Report,1997 1

I

• Staff participated in the Vendor Inspection of the of specialize,d equipment to MEPNS and G AN Siemens Fuels and provided expertise in the training locations necessary m suppon of develop-areas of BWR thermal-hydraulics, sofm : QA ment and implementation of their regulatory and training systems development to tnis major training programs.

team inspection. .

As a result of technical assistance provided through

• Staff provided briefings on BWR and PWR Priority 5, GAN has made significant progress in technology and Emergency Operating Proce- the overall strengthening of its regulatory training dures for Commissioner McGaffigan. program. A GAN regulatory training center has been established in the city of Novovoronezh,

• Staff panicipated in the IAEA OS ART inspec-tion of the Qinsan Nuclear Power Plant in China. ugsia within the Don Region of GAN. This is the national training center of G.AN in the sense that

• Staff provided technical assistance to NRR by the TTC is the national training center of the NRC.

completing an evaluation of the ORNL re iew of The GAN training center has been staffed with the latest revision of the BWROC EPG/ SAG permanent personnel including some with reactor guidance, inspection and radiation protection exp n se and

. experience. Suitable funding has been ncie

• Webmaster duties for AEOD were accomplished available within the GAN budget for development by a member of the simulator engineering staff.

of a number of courses that will serve as the Development of a website for AEOD, TTD, and curriculum of the GAN training center for the next SPD has been accomplished and the website is several of years, now in the maintenance phase. Maintenance of a previously developed site for IRD has also been The last formal activity under Priority 5 is planned assumed by the Webmaster. Documents included for October 1997. Five experts (instructors fa om in these sites are the AEOD Annual Report for GAN regional ofGees) will visit the Technical 1995, numerous studies and reports, and an Training Center, Region 11 OfGee and the online catalog of TfD courses. Sequoyah Nuclear Plant. The purpose of the visit is for sertior GAN regional personnel to see first hand how the NRC trains inspectors and to discuss 4.3 Lisbon Initiative Technical GAN plans fer implementing small trammg Assistance organizations in each region.

TTD continued to be actively involved in technical Joint activity within the present Priority has alkred assistance to Russia and Ukraine under the Lisbon GAN to ensure a systematic approach to reFulatory Initiative. Ukrainian Priority 2 and Russian Priority personnel training including training in the GAN 5, Establishment of Regulatory Training Programs, TC as well as GAN regional and inspection offices, have assisted the Ministry for Environmental Protec- After completion of the October 1997 activities, tion and Nuclear Safety (MEPNS) of Ukraine both the USNRC and GAN plan that Russian (formerly the Ukrainian State Committee on Nuclear Priority 5 will be successfully completed. Co-and Radiation Safety (SCNRS)) and Gosatomnadzor operation within Priority 5 will be maintained in the (GAN) of Russia in the establishment of comprehen- form of NRC TTD consultations and mutual sive systems for training and qualification of MEPNS discussions on the training prgrams and courses and GAN technical personnel. developed by the GAN TC .

Work in these priorities has included transfer c,f the Implementation of Ukrainian Priority 2 has been methodology and practical application of activities very successful in upgrading the training ability of associated with the principles of the systems the Ukraine Radiation Training Center (URTC) apprcach to training, transfer of knowledge of manpower development of ULrainian Regulatory contemporary information and technology to Body. The training courses which have been carried MEPNS and GAN specialists to supplement and out, bdefings in different areas of nuclear and enhance their knowledge and skills in several radiation safety, have served to familiarize Ukrai-scientific and engineering specialties, and delivery nian specialists with U.S. safety culture. The NUREG-1272, Vol.11, No.3 14

Technical Training equipment which has been transferred has become Eighteen representatives from nuclear generating the base for implementation of modern technology plants and regulatory agencies in Russia, Ukraine, in the training process. The assistance in prepara- Hungary, Slovakia, Bulgarie, Hungary, and the tion of training manuals provided by assignments of Czech Republic spent a weetat the Technical URTC personnel at the Technical Trainmg Center Training Center November e8,1996 to learn about has been effective in implementing knowledge m pressurized water reactor emergency operating nuclear and radiation safety. After completion of the procedures. The visit was coordinated by DOE as 1997 activities, both the USNRC and NRA plan part of an effort aimr ' at improving reactor safety that Ukrainian Priority 2 will be successfully e Russia, Ukraine m . tern Europe. The TTC completed. Co-operation within Priority 2 will be classoom and simuw. .acilities were utilized to ,

maintained in the form of NRC TD consultations discuss development, implementation, and training I and mutual discussions on the trai'.iing programs aspects of Westinghouse einergency operating and courses developed by the UF.FC. procedures. TfD staff assisted personnel from Pacific Northwest Laboratory in simulator in addition to the two Lisbon Initiative technical w Ikthroughs and demonstrations.

assistance projects mentioned above, two others have evolved. Under the framework of Russian Priority 5.1, the NRC has provided two Analytical 4.4 Starr nevelopment Simulators to GAN for trairhg oi regulatory pmeni.d. Under the frr..ework of Ukraine Priority TTD stad actively participated in a variety of 2.1, NRC has provid. J one Analytical Simulator to professional meetings. TfD staff panicipation MEPNS for trainir.g of regulatory personnel. ranged from full and active participation in the conduct of the meeting to attendance as general The scope of this technical assistance included attendees. Attendance at meetings and conferences development of a statement of work, establishment is supponed based upon their relevance to the TfD of a contract, contractor development of specialized programmatic goals. Attending professional and simulation software, and delivery of equipment- technical meetings assists TfD staffin maintaining The work in this priority also involved assisting their technical and regulatory knowledge, skills and GAN and MEPNS in assuring that the Analytical abilities current with the state of the art / industry.

Simulators are functional and adequately represent the intended reactor designs and includes training TfD staff attended the Health Physics Society of designated GAN and MEPNS staff who will use annual meeting. In addition, TfD staff completed a and maintain the Analytical Simulators. term as a member of the ABHP examination panel, another is a member of the Health Physics Society The work also included the prioritized development Academic Education Committee and the Health of additional Analytical Simuletor software loads, Physics Society N13.49 Working Group, and another establishment of Analytical Simulator hardware at is a member of the ANSI 13.36 committee " Core di fferent GAN locations and the construction of Training in Radiation Protection for Workers". TfD simulator facilities at GAN Headquarters in Mos- staff also attended an EPRI workshop on effective cow and the Don Regional Headquarters in the Don external dose equivalent held in August 1997.

Region . A third simulator and associated facility will be provided for the North Eastern Regional TTD staff continued to be active in the Armor and Headquarters near St. Petersburg, Russia. Also Protective Systems Working Group (APSWG),

included, is the prioritized development, implemen_ attending several meetings and participating in a tation of additional Analytical Simulator software special APSWG field test.TfD staff also attended loads and the construction of a simulator facility in symp sia and seminars on computer based train-Kiev, Ukraine for MEPNS. ing technology and the conference on Steam Generator Tube Degradation. TTD staff partici-In support of Russian Priority 5.1 and Ukraine pated in the Society for Computer Simulation Priority 2.1, a number of project review meetings Spring Multi-Conference in April 1997. TTD staff and audits have taken place in Russia, Ukraine, and served on the conference committee and partici-the U.S. pated as a session chair.

15 Other Activities

AEOD Annual Report,1997 TTD staff actively panicipated in the Aherican 7TD stad attended two conferences sponsored by Nuclear Society (ANS) winter and summer the Americar, Society for Training and Develop-meetings, leading a seminar on preventive mainte- ment ( ASTD): The 1997 International Conference nance at the summer meeting.'lTD staff ah 9 and Exposition and the 1997 Technical Training served on the national publication stcering con- Conference and Exposition. The conferences mittee, national professional des clopment coor di- is reased staff knowledge of new approaches to nation committee, and as chair on ," e stional de ,Jgning, evaluating, delivering and managing planning committee of the ANS."4T': staff also tecmical training. Emphasis during the coriferences served IEEE as an American Boars for Engineer- was on distance learning technologies and their 2ng and Technology +. valuator N; e,e Electrical applicabili .y to NRC technical training.

12ngineering curriculum.

1 NUREG-1272. Vol.11, No.3 16

'd 4 .

h

! i 2

i 4

)

APPENDIX A i 4

Instructional-Hour Totals 1

3 .

i l l

3 7

4 l

E 1

J N

d o

Y 2

4 3

5 4

1 1

a 1

1 t

3 k

Technical Training 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-4 Key QTY = Quantity of Courses C-W = Course-Weeks IH = Instructional-Hours 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 IP = international Programs Personnel (Foreign Nationals)

AS = Agreement States SP = State Programs OTH = Other NRC Offices or Other Agencies TOT = Total A-iii Appendix A

. ..- _. . . - - . . - . .. ~ .

Table A-1 Reactor Technology Instructional-Hour Totals by Course Group R1 R2 R3 R4 NRR AEOD NMSS RES IP AS SP OTH TOT COURSE QTY C-W IH IH IH IH IH IH IH IH IH IH IH - IH IH Technology (100 Level) 3 3 264 0 396 33 198 33 0 132 0 0 0 33 1089 Technology (200 Level) 1 3 0 0 0 0 630 0 0 0 0 0 0 0 630 Technology (300 Level) 4 12 1920 768 1152 288 864 0 0 192 768 0 0 0 5952 Advanced Technology (500 Level) 4 8 1360 544 1088 136 544 0 0 136 340 0 0 0 4148 Simulator (Series) iI 22 1400 560 910 140 560 0 0 70 350 0 0 0 3990 ,

Simulator (Refresher) 17 17 350 700 1085 665 175 35 35 0 0 0 0 0 3N5 Westinghouse Nuclear Engineering i 2 0 140 0 70 0 210 0 0 0 0 0 0 420 GE Maintenance Training Overview 1 1 0 34 34 0 136 0 0 0 0 0 0 0 2M Westinghouse Maintenance Overview 1 I 34 34 34 34 238 34 0 0 0 0 0 0 408 Technology Review (900 Level) 1I II 245 420 245 735 350 105 35 35 35 0 0 0 2205 CE Cross Training (R-325C) 1 3 285 190 95 380 95 0 0 0 0 0 0 0 1045 B&W Cross Training (R-326C) 1 3 95 285 190 95 0 0 0 0 0 0 0 0 665

f. Reator Concepts (R-100) 3 3 84 0 0 28 70 0 84 14 0 0 0 210 490 Perspectives on Reactor Safety (R-800) 1 I 70 35 105 0 175 0 0 0 35 0 0 0 420 i Reactor Technology Totals 60 90 6107 3710 5334 2604 4035 417 154 579 1528 0 0 243 24711 k

l

% D'

? 5

& 5-

> g

Table A-?. Reactor Technology Instructional-Hour Totals by Course Qi;

]

g 8 O RI R2 R3 R4 NRR AEOD NMSS RES IP AS SP OTH TOT >

h COURSE QTY CW IH IH IH IH IH IH IH IH IH IH IH IH IH $

n a g GE BWR/6 Technology (R-106B) 1 1 132 0 66 33 0 33 0 0 0 0 0 33 297 g

- GE BWR/4 Technology (R-304B) 2 6 960 288 480 0 192 0 0 96 192 0 0 0 2208 E E GE BWR/4 Advanced Technology (R-5mB) 2 4 680 204 544 0 136 0 0 68 68 0 0 0 1700

$ GE BWR/4 Simulator (R-624B) 4 8 700 140 420 0 70 0 0 0 70 0 0 0 1400 g L GE BWR/4 Simulator Refresher (R-704B) 5 5 70 70 490 105 105 0 0 0 0 0 0 0 840 $

GE BW R/4 Simulator Refresher (R-706B) I 1 0 0 70 105 0 0 0 0 0 0 0 0 175 GE Maintenance Training Overview (R-802B) I 1 0 34 34 0 136 0 0 0 0 0 0 0 2M GE BWR/4 Technology Review (R-904B) 3 3 35 175 105 140 140 0 0 0 0 0 0 0 595 GE Subtotals 19 29 257. 911 2209 383 779 33 0 164 330 0 0 33 7419

]

Westinghouse Technology (R-104P) 2 2 132 0 330 0 198 0 0 132 0 0 0 0 792 y Westinghouse Technology (R-200P) 1 3 0 0 0 0 630 0 0 0 0 0 0 0 630 la Westinghouse Technology (R-3NP) 2 6 960 480 672 288 672 0 0 96 576 0 0 0 3744 Westinghouse Advanced Technology (R-SMP) 2 4 680 340 544 136 408 0 0 68 272 0 0 0 2448 Westinghouse Simulator (R-624P) 7 14 700 420 490 140 490 0 0 70 280 0 0 0 2590 Westinghouse Simulator Refresher (R-704P) 8 8 280 490 350 315 35 35 35 0 0 0 0 0 1540 Westinghouse Nuclear Engineering (R-801P) 1 2 0 140 0 70 0 210 0 0 0 0 0 0 420 Westinghouse Maintenance Overview (R-802P) 1 I 34 34 34 34 238 34 0 0 0 0 0 0 408 Westinghouse Technology Review (R-904P) 7 7 210 245 140 490 175 105 35 35 35 0 0 0 1470 Westinghouse Subtotals 31 47 2996 2149 2560 1473 2846 384 70 401 1163 0 0 0 14042 CE Cross Training (R-325C) 1 3 285 190 95 380 95 0 0 0 0 0 0 0 1045 CE Simulator Refresher (R-705P) 2 2 0 105 105 iG5 35 0 0 0 0 0 0 0 350 CE Technology Review (R-905P) I 1 0 0 0 105 35 0 0 0 0 0 0 0 140 Combustion Engineering Subtotals 4 6 285 295 200 590 165 0 0 0 0 0 0 0 1535 l l

l l

Table A-2 Reactor Technology Instructional-Hour Totals by Course RI R2 R3 R4 NRR AEOD NMSS RES IP AS SP OTH TOT COURSE QTY C-W IH III IH III IH IH IH III IH IH IH IH IH B&W Cross Training (R-326C) 1 3 95 285 190 95 0 0 0 0 0 0 0 0 665 B&W Si'.nulator Refresher (R-706P) I i 0 35 70 35 0 0 0 0 0 0 0 0 140 Babcock & Wilcox Subtotals 2 4 95 320 260 130 0 0 0 0 0 0 0 0 805 Reactor Concepts (R-100) 3 3 84 0 0 28 70 0 84 14 0 0 0 210 490 Perspectives on Reactor Safety (R-800) 1 1 70 35 105 0 175 0 0 0 35 0 0 0 420 Generic Reactor Technology Subtotals 4 4 154 35 105 28 245 0 84 !4 35 0 0 210 910 Reactor Technology Totals 60 90 6107 3710 5334 2604 4035 417 154 579 1528 0 0 243 24711 Q

f I

k I '

% D' 2 i .

E B w g-

> 5' oo

Table A-3 Specialized Technical'IYaining Instructional-HourTotals by Course q; g

El a R1 R2 R3 R4 NRR AEOD NMSS RES IP AS SP OTH TOT >

IH IH IH IH IH IH IH IH IH IH IH M L

u COURSE QTY C-W IH III o

U

-d >

o

$ Probabilistic Risk Assessment

[ PRA Basics for Regulatory Applications 1 1 105 42 42 21 147 0 21 42 0 0 0 21 441 h

~

2 42 56 56 28 126 28 14 14 0 0 0 42 406 Z

PRA Insights into an IPE 2 f PRA for Technical Managers 2 2 0 42 0 0 252 21 21 21 21 0 63 210 651 ] ,

P

" 28 0 0 0 0 0 84 420 3 System Modeling Techniques 1 I 84 56 28 56 84 IRRAS Basics 2 2 0 28 0 28 112 28 56 140 0 0 0 168 560 2 2 0 0 0 28 28 56 0 28 0 0 0 0 140 Advanced IRRAS Human Reliability Assessment 1 1 84 105 21 63 42 0 0 21 0 0 0 21 357 External Events i 1 0 0 0 0 105 21 84 84 0 0 0 21 315 Accidert Progression Analysis 1 1 42 0 0 0 189 21 0 0 0 0 0 0 252 Accident Consequence Analysis 1 1 0 0 0 0 63 0 21 21 0 0 0 21 126 i 84 56 84 84 84 0 0 0 0 0 0 0 392 y Fisk Assessment in Event Evaluation 1 i 441 385 231 308 1232 203 217 371 21 0 63 588 4060 PRA Subtotals 15 15 Engineering Support Technology 2 0 0 268 67 67 134 0 0 0 0 0 0 536 Welding Technology and Codes 1 2 0 0 268 67 67 134 0 0 0 0 0 0 536 Engineering Support Subtotals 1 Radiation Protection 4 4 0 0 0 56 308 14 224 0 0 0 28 28 658 Site AccessTraining Site Access RefresherTraining 5 5 0 7 0 0 581 70 217 7 0 0 0 14 896 0 0 0 0 0 0 52 0 0 0 0 0 52 Radiation Worker Training 1 1 O O O 32 0 0 0 0 0 0 0 0 32 In-Place Filter Testing 1 I

ME.

Table A-3 Specialized Technical Waining Instructional-Hour Totals by Course R1 R2 R3 R4 NRR AEOD NMSS RES IP AS SP OTH TOT COURSE QTY C-W IH IH IH IH IH IH IH IH IH IH IH IH IH Apphed Health Physics 2 8 0 0 0 172 0 0 860 0 0 0 2236 0 3268 General Decry of Gamma Spectroscopy 2 2 0 0 35 0 0 0 0 0 0 0 0 0 35 Introduction to Health Physics 1 I O 70 0 0 35 0 210 35 0 245 0 315 910 Air Samphng for Radioactive Materials 1 1 0 35 140 105 35 0 35 0 0 315 0 0 665 Radiological Suneys for Decommissioning 2 2 56 0 0 84 14 0 210 0 0 196 14 56 630 llcalth Physics Technology 1 2 0 0 603 0 0 0 134 0 0 871 0 0 1608 Radwaste Management i I 140 140 140 35 0 0 70 0 0 0 0 0 525 Emergency Preparedness I i 140 70 105 105 105 70 0 0 140 0 0 0 735 Radiological Emergency Response Operations 2 2 0 64 32 32 0 0 0 0 0 0 0 0 128 Diagnostic and herapeutic Nuclear Medicine i I 36 0 0 0 0 0 36 0 0 468 0 0 540 Safety Aspects ofIndustrial Radiography 1 1 0 35 105 35 35 0 0 0 0 350 35 0 595 Radiological Accident Assessment i I 32 0 0 0 0 0 0 0 0 0 0 0 32

> Transportation of Radioactive Materials 1 1 70 0 175 70 35 35 210 0 0 350 0 35 980 llP in Radiation Accidents 1 1 0 0 0 64 0 0 0 32 0 0 0 0 96 Respiratory Protection i 1 0 0 0 35 0 0 0 J 0 0 0 0 35 Internal Dosimetry and Whole Body Counting i 1 0 0 420 0 0 0 70 35 0 0 0 0 525 Teletherapy / Brachytherapy i i 144 36 0 36 0 0 108 72 0 144 72 0 612 Safety Aspects of Well Logging 1 1 0 0 108 0 0 0 72 0 0 540 36 0 756 Radiation Protection Subtotals 33 40 618 457 18 - 861 1148 189 2508 181 140 3479 2421 448 14313 Fuel Cycle Techm> logy Nuclear Criticality Safety i I 35 35 105 0 0 0 490 0 140 0 0 0 805 IIP Practices for Uranium Recovery i I o O O 42 0 0 336 0 0 84 0 42 504 Fuel Cycle Technology 1 1 0 84 56 28 28 84 504 0 0 0 0 84 868 g Fire Protection for Fuel Cycle Facilities 1 i 0 84 21 0 21 0 SM 0 0 0 0 0 630 S 2.

> Fuel Cycle Suhtotals 4 4 35 203 182 70 49 84 1834 0 140 84 0 126 2807 $

4 H E E

e. E' x

> g-tra q ' _; p y . . :.; . i;= gn , ._. -:. 3 7 ;.a..w.3n:;.

q f ;x . :.j, s- :;$-'!(( : m: ;-

yf.^' } : ; ' '.' ' - [?;~y , [&ny.'

--- "-[ v '.= ;__.,.;?Y--}_,.l'lf:l m.x.a + x a v~~

                                                 .                               .                                                            ~n.         ---

Z Table A-3 Specialized Technical'IYaining Instructional-flourTotals by Course C g b " o RI R2 R3 R4 NRR AEOD NMSS RES IP AS SP OTH TOT > ,

4. COURSE QTY C-W IH IH IH IH IH IH IH IH IH IH IH IH IH l 5

0 g - Regulatory Skills g Fundamentals ofinspection 2 2 84 140 448 112 224 0 280 0 0 0 0 28 1316 E .C Field Techniques and Regulatory Processes 1 1 66 165 66 66 33 0 0 0 0 0 0 0 3% $ Operating Examination Techniques 2 2 536 134 134 0 0 0 0 0 0 0 0 0 804 .g 'a t Inspection Procedures  ! I O O O O O O 72 0 0 540 36 252 900 $ Licensing Practices & Procedures 1 1 288 0 0 0 36 0 36 36 0 432 72 72 972 G5HA Indoctrination 4 4 96 52 104 4 32 0 276 4 0 0 0 4 572 Root Causedncident Investigation Workshop 6 6 420 490 525 70 210 35 910 0 140 0 70 0 2870 Human Performance Investigation Wc rkshop 1 1 0 0 91 0 0 0 0 0 0 0 0 0 91 Inspecting for Performance 5 5 306 108 288 72 198 72 162 0 0 18 0 18 1242 Inspecting for Performance-Materials 1 36 36 90 0 0 0 0 0 0 0 18 0 180 y Regulatory Skills Subtotals 23 24 1832 1125 1746 324 733 107 1736 40 140 990 196 374 9343 6 Specializeel Technical Training Totals 76 85 2926 2170 4290 1630 3229 717 6295 592 4414553 2680 1536 31059

APPENDIX B Student Totals

Technical Training CONTENTS Tables Page B-1 Reactor Technology Student Totals by Course. . . . B-1 B-2 Specialized Technical Training Student Totals by Course. . .B-3 i l Key QTY = Quantity of Courses C-W = Quantity of Course-Weeks

 #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 .daterial Safety and Safeguards RES = Office of Nuckar Regulatory Research IP = International Programs Personnel (Foreign Nationals) AS = Agreement States SP = State Programs OTH = Other NRC Offices or Other Agencies TOT = Total l B-iii Appendix B

Table B-1 Reactor Technology Student Totals by Course R1 R2 R3 R4 NRR AEOD NMSS RES IP AS SP OTH TOT COURSE QTY C-W #S #S #S #S #S #S #S #S #S #S #S #S #S General Electric Technology GE BWR/6 Technology (R-106B) I i 4 0 2 0 0 0 0 0 0 1 1 1 9 GE BWR/4 Technology (R-304B) 2 6 10 3 5 0 2 0 0 2 0 0 0 1 23 GE BWR/4 Advanced Technology (R-501B) 2 4 10 3 8 0 2 0 0 1 1 0 0 0 25 GE BWR/4 Simulator (R-624B) 4 8 10 2 6 0 1 0 0 0 1 0 0 0 20 GE BWR/4 Simulator Refresher (R-704B) 5 5 2 2 14 3 3 0 0 0 0 0 0 0 24 GE BWR/4 Simulator Refresher (R-7%B) 1 1 0 0 2 3 0 0 0 0 0 0 0 0 5 GE Maintenance Training Overview (R-802B) 1 1 0 I I O 4 0 0 0 0 0 0 0 6 GE BWR/4 Technology Review (R-904B) 3 3 1 5 3 4 4 0 0 0 0 0 0 0 17 GE Subtotals 19 29 37 16 41 11 16 1 0 2 4 0 0 1 129

   $                       Westinghouse Technology Westinghouse Technology (R-104P)                   2     2          4  0  10    0              6     0                                 0      4            0     0  0      0                  24 Westinghouse Technology (R-200P)                    1    3          0  0    0   0              6     0                                 0      0            0     0  0      0                      6 Westinghouse Technology (R-304P)                   2     6        10   5    7   3              7     0                                 0      1            6     0  0      0                  39 Westinghouse Advanced Technology (R-504P)          2     4        10   5    8   2              6     0                                 0      1            4     0  0      0                  36 Westinghouse Simulator (R-624P)                    7    14        10   6    7   2              7     0                                 0                   4     0  0      0 1                                               37 Westinghouse Simulator Refresher (R-704P)          8     8          8 14  10    9              1     1                                  1     0            0     0  0      0                 44 Westinghouse Nuclear Engineering (R-80lP)          1     2          0  2    0   1              0     3                                 0      0            0     0  0      0                      6 Westinghouse Maintenance Overview (R-802P)         i     1          1  1    1   1              7     1                                0       0            0     0  0      0                   12 Westinghouse Technology Review                     7     7          6  7    4  14              5     3                                  1     1            1     0  0      0                 42 Westinghouse Subtotals                            31    47        49  40  47   32             45     8                                2       8       15         0  0      0        246             g w

2,

  =                                                                                                                                                                                                                            4 ,

l to e L_ _ _ _ _ _ _ . _ _ _ _ _. - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Z Table B-1 Reactor Technology Student Totals by Course C g b " o Rt R2 R3 R4 INRR AEOD NMSS RES IP AS SP OTil TOT > h COURSE QTY C-W #S #S #S #S #S #S #S #S #S #S #S #S #S $ n 0 g Comimstion EngineeringTechnology CE

  "                                                                                                                                     g Cross Training (R-325C)                  1        3  3       2            1    4    1     0    0       0  0   0     0     0   1I   g
  ~

CE Simulator Refresher (R-705P) 2 1 0 3 3 3 1 0 0 0 0 0 0 0 10 5 CE Technology Review (R-905P) I 1 0 0 0 3 1 0 0 0 0 0 0 0 4 j W

1 Comhustion Engineering Subtotals 4 6 3 5 4 10 3 0 0 0 0 0 0 0 25 Babcock & Wilcox Technology B&W Cross Training (R-326C) 1 3 1 3 2 1 0 0 0 0 0 0 0 0 7 B&W Simulator Refresher (R-706P) I 1 0 1 2 1 0 0 0 0 0 0 0 0 4 Babcock & Wilcox Subtotals 2 4 1 4 4 2 0 0 0 0 0 0 0 0 II tn la Generic Reactor Technology Reactor Concepts (R-100) 3 3 6 0 0 2 5 0 6 1 0 0 0 15 35 Perspectives on Reactor Safety (R-800) 1 I 2 1 3 0 5 0 0 0 1 0 0 0 12 Generic RT Suhtotals 4 4 8 1 3 2 10 0 6 1 1 0 0 15 47 I

Reactor Technology Totals 60 90 98 66 99 57 74 9 8 II 20 0 0 16 458 j i i i

Table B-2 Specialized Technical Training Student Totals by Course R1 R2 R3 R4 NRR AEOD NMSS RES IP AS SP OTil TOT-COURSE QTY C-W #S #S #S #S #S #S #S #S #S #S #S #S #S Probabilistic Risk Assessment PRA Basics for Regulatory Applications 1 1 5 2 2 1 7 0 1 2 0 0 0 1 21 PRA Insights into an IPE 2 2 3 4 4 2 9 2 1 1 0 0 0 3 29 PRA for Technical Managers 2 2 0 2 0 0 12 I 1 1 1 0 3 10 31 System Modeling Techniques  ! I 3 2 1 2 3 1 0 0 0 0 0 3 15 IRRAS Basics 2 2 0 1 0 1 4 1 2 5 0 0 0 6 20 Advanet.d IRRAS 2 2 0 0 0 1 1 2 0 1 0 0 0 0 5 liuman Reliab;'ity Assessment 1 I 4 5 1 3 2 0 0 1 0 0 0 1 17 External Events 1 1 0 0 0 0 5 1 4 4 0 0 0 I 15 Accident Progression Analysis  ! I 2 0 0 0 9 1 0 0 0 0 0 0 12 Accident Consequence Ar;alysis I l 0 0 0 0 3 0 1 1 0 0 0 1 6 to Risk Assessment in Esent Evaluation i 1 3 2 3 3 3 0 0 0 0 0 0 0 14 s PRA Subtotals 15 15 20 18 11 13 58 9 10 16 1 0 3 26 185 Engineering Support Technology Welding Technology and Cales 1 2 0 0 4 1 1 2 0 0 0 0 0 0 8 Engineering Support Suhtotals 1 2 0 0 4 1 1 2 0 0 0 0 0 0 8 Radiation Protection Site AccessTraining 4 4 0 0 0 4 22 1 16 0 0 0 2 2 47 1 Site Access Refresher Training 5 5 0 1 0 0 83 10 31 1 0 0 0 2 128 i Radiation WorkerTraining i 1 0 0 0 0 0 0 13 0 0 0 0 0 13 g In-Place FilterTesting 1 1 0 0 0 1 0 0 0 0 0 0 0 0 1 E E'

             'O 2=                                                                                                                                                                                        @

u

b. b~

x g-ID OQ l------.__--- - - - _ . _ _ - . _ _ _ _ _ - - - - _ _ . _ _ -

g Table B-2 Specitlized Technical Trrining Student Totals by Course G x s $ Rt R2 R3 R4 NRR AEOD NMSS RES IP AS SP OTil TOT > y COURSE QTY C-W #S #S #S #S #S #S #S #S #S #S #S #3 #S $ n 0 h Applied llealth Physics 2 8 0 0 0 1 0 0 5 0 0 0 13 0 19 { General Theory of Gamma Spectroscopy 2 2 0 0 1 0 0 0 0 0 0 0 0 0 1 { h Introduction to liealth Physics 1 I O 2 0 0 1 0 6 1 0 7 0 9 26 g Air Sampling for Radioactive hiaterials Radiological Surveys in Support 1 1 0 1 4 3 1 0 1 0 0 9 0 0 19

                                                                                                                                    }

of Det ammissioning 2 2 4 0 0 6 1 0 15 0 0 14 1 4 45 Ilealth Physics Technology 1 2 0 0 9 0 0 0 2 0 0 13 0 0 24 Radwaste hianagement i 1 4 4 4 1 0 0 2 0 0 0 0 0 15 Emergency Preparedness i I 4 2 3 3 3 2 0 0 4 0 0 0 21 Radiological Emergency Response , and Operations 2 2 0 2 1 1 0 0 0 0 0 0 0 0 4 k Diagnostic and Therapeutic Nuclear hiedicine 1 1 1 0 0 0 0 0 1 0 0 13 0 0 15 Safety Aspects of Industrail Radiography 1 i 0 I 3 1 1 0 0 0 0 10 1 0 17 Radiological Accident Assessment i I I O O O O O O O O O O O I Transportation of Radioactive hiaterials 1 1 2 0 5 2 1 1 6 0 0 10 0 1 28 l IIP in Radiation Accidents 1 I O O O 2 0 0 C 1 0 0 0 0 3 Respiratory Protection 1 1 0 0 0 1 0 0 0 0 0 0 0 0 1 Internal Dosimetry and Whole Body Counting 1 I O O 12 0 0 0 2 1 0 0 0 0 15 Teletherapy / Brachytherapy i I 4 1 0 1 0 0 3 2 0 4 2 0 17 Safety Aspects of Well Logging 1 1 0 0 3 0 0 0 2 0 0 15 1 0 21 Radiation Protection Subtotals 33 40 20 14 45 27 113 14 105 6 4 95 20 1d- 481

Table B-2 Specialized Technical Training Student Totals by Course Rt R2 R3 R4 NRR AEOD NMSS RES IP AS SP OTH TOT COURSE QTY C-W #S #S #S #S #S #5 #S #S #S ' #S #S #S #S Fuel Cycle Technology Nuclear Critictlity Safety i I 1 1 3 0 0 0 14 0 4 0 0 0 23 IIP Practices for Uranium Recovery 1 1 0 0 0 3 0 0 24 0 0 6 0 3 36 Fuel Cycle Technology i I O 3 2 I I 3 18 0 0 0 0 3 31 Fire Protection for Fuel Cycle Facilities 1 I O 4 1 0 1 0 24 0 0 0 0 0 30 Fuel Cycle Subtotals 4 4 I 8 6 4 2 3 80 0 4 6 0 6 120 I Regulatory Skills Fundamentals ofInspection 2 2 3 5 16 4 8 0 i0 0 0 0 0 1 47 Field Techniques and Regulatory Processes 1 I 2 5 2 2 1 0 0 0 0 0 0 0 12 { Operating Examination Techniques 2 2 8 2 2 0 0 0 0 0 0 0 0 0 12 Inspection Procedures i I O O O O O O 2 0 0 15 1 7 25 Licensing Practices & Procedures 1 1 8 0 0 0 1 0 1 1 0 12 2 2 27 OSIIA Indoctrination 4 4 24 13 26 I 8 0 69 1 0 0 0 1 143 Root Cause/ Incident Investigation Workshop 6 6 12 14 15 2 6 1 26 0 4 0 2 0 82 Iluman Performance Investigation Workshop 1 1 0 0 13 0 0 0 0 0 0 0 0 0 13 Inspecting for Performance 5 5 17 6 16 4 11 4 9 0 0 1 0 1 69 Inspecting for Performance 1 2 2 5 0 0 0 0 0 0 0 1 0 10 Regulatory Skills Subtotals 23 24 76 47 95 13 35 5 117 2 4 28 6 12 440 Specialized Technical Training Totals 76 85 117 87 58 209 33 312 13 129 62 1234 161 24 29 g 2.

 >                                                                                                                                                                                                                 0 3
 =>                                                                                                                                                                                                                5 u

tn 55

NRC FCRM 335 U S NUCLEAR REGULATORY COMMISSION 1. REPORT NUMBER (2 89) (Asmgned by NRC, Add %)l., Supp, j NFCM 1102, Rev., and Addendum Numbers, if any) 32ot aro2 BIBLIOGRAPHIC DATA SHEET l cSee marruccons on ine rev.=> NUREG-1272 a ma ANDsuema Vol.11, No. 3 3 DATE REPORT PUBubMED I Office for Analysis and Evaluation of Operational Data M NTH YEAR 1997 Annual Report l November 1998 4 FIN OR GRANT NUMBER 6 AUTHORf5) 6 TYPE OF REPORT

7. PERIOD COVERED (Inciumvo Dates)

FY 1997 e PERFOHMING OHGANil.ATION - NAME AND ADDRESS (if NRC, provide Divison. Othee or Region, U S Nucteer Regu6atory Commismon, and maling aooress,if contractor, provide nemt and malen0 eddr*es ) Office for Analysis and Evaluation Operational Data U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

                                                                                                                                                                                                                   ]

9 bPONSORING ORGANilATION . NAME AND ADDRESS (if NRC, type "Same es above*; Il contractor. provide NRC Dnnmon, Office or Region, U S. Nuclear Regulatory Commismon, and mailmg androns } Same as in item 8 i 10 buPPLEMENTARY NOTE 5

11. A8STRACT (200 words or toes)

This annual report of the U.S. Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operat!onal Data (AEOD) describes activities conducted during 1997. The report is published in three parts. NUREG-1T/2, Vol.11, No.1, covers power 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 re-port 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.11, No. 2, covers nuclear materials and presents a review of the events and concerns during 1997 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 summarizes both the Incident Investigation Team and Augmented Inspection Team reports. Each volume contains a list of the AEOD reports issued from CY 1980 through 1997. NUREG-1272, Vol.11, No. 3, covers technical training and presents the activities of the Technical Training Center in support of the NRC's mission in 1997.

12. KEY WORDS/DESCRiPTORS (Dat words or phrases that will asmat researchers m locatmg the report ) 13 AVAILABluTYSTATEMENT Unlimited technical training simulator .4 SECURITYCLASSWCATION reactor technology training engineering support training W P=m probabilistic risk assessment training radiation protection training Unclassified fuel cycle training safeguards training ( rni, a,por 3 regulatory skills training Agreement State training Unclassified digital instrumentation and control training GE BWR/4 simulator i. NUMeeR O, Pow,  ;

Westinghouse simulator Cornubustion Engineering simulator j nuclear engineering workstation simulator Lisbon Initiative technical assistance j 16 PRCE d NRC FORM 335 p.89) -

4 a Federal Recycling Program

N ,c : py^ x g

                                                                                                                                                        ~

f.[~ [Y997 - w ;. -~.w

                                                                                                                                                                                       - ~

_- .w,. g- -

                                                             -                    -                                                            -                                                                                                                                                                                                                                                                                                                                                                                                                            c,
                                                                                                                                                                                                                                                                                                                                   . , ~ .~..y
                                                                                                                                                                                                                                                                                                                                                                                            .c                                                                                                                                                      n ,w;

(.v w.;;,_ ,q g .;; s

                                                                                                        ,4;,f      a .y         _                                                                                                                                                       :                 --c.        -                                                            -

g. . . nm'. ,p _-.f % . .

c .: o-a. e x .y_ -m ~ , m c.,y - m .m - wm-

  ~.            rc:                 -. e            -

r. .m - _ o x '

                                                                                                           *' 7 _

c q ,,y"- '"_y& t.m,. a, , . , xp 4. w s

                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                  ., m'"<ws.. *                                    -
                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                     .M3. s                                  --

(.J . , f'-A'., '

                  ) '       y

[g(s'.'

                                   -[..    .,
                                                            's:-D _7-'
                                                                             ,g..,.'4.',l
                                                                                             }bi   '

I N gp. ,f.,' O"'-

                                                                                                                                                                                                                                                                                                                             , f y.
                                                                                                                                                                                                                                                                                                                                                                ,'7_h'_'_"'.

s

                                                                                                                                                                                                                                                                                                                                                                                                            --""'y-       ,.
                                                                                                                                                                                                                                                                                                                                                                                                                                                                       +

y ['--i'-) .. ( s..-.

                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                             ., ' - vC

2. ,f' a"'

                                                                                                                                                                              .c.
                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                             ?
                                                                                                                                                                               .g,                                                                                                                                                            6                                                               '-                                                                                                      .l.g,'                                                                 i
                                                                                                                                                                                                                                                                                                                                                                                ~

gyQ,_ ' ly x.,,,- n. .  ; -

    ';:;r~.y ( en
                                                                                                                                                                                                                                                                                                                                                                                                                                                                           ~
                                                                                                                                                    , _                                                                                                                  g                                              '~.::         @ 3 g.;;: y ::_              .                                                                                                                                                                                                                       s
                                                ..,       Q

_' 1 - .% L:- .

                                                                                                                                                                                                              ,                                                                ,; Q                                           * - uTL
                                                                                                                                                                                                                                                                                                                                            ~
                                                                                                                                                                                                                                                                                                                                                                                                   . 4 y-; &.
                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                           .n a __
                                                                                                                                                                                                                                                              -~@~-                                                                                                  j@ [MC
                                 - ~ l M~ UNITED STATES                                                                      1-                                                          .

i^hM

                                                                                                                                                                                                                                                                                                               ~

W

                                                                                                                                                                                                                                                                                                                                                                                                                                                         ~ NSFutsTctAssasud.Y[                                                                                                                   $-

tyjp NUCLEAR REGUULTORY COSMRSSION ^ ' T6 M m D M POSTAGE AND FEES PAID h. USNHC- '

                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                 %                         2 P -                                          ~

WASHINGTON;DC 205554001:

                                                                                .                                                               v.                 .
                                                                                                                                                                        % f-                                                -a-                             , 1J y_

K , -

                                                                                                                                                                                                                                                                                                                                                                                            ~

y - p gpRV'T N O. G W

                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                              =             f  s M gy:,s..                                                                                                                                                        - .
                                                                                                                                                                                                                                                                    .t       -
     -y.                                                                                                                                                                                                                                                              '
                                                                                                                                                                                                                                                                                                        ^

f 2_..

                                    .-w v                          -
                                                                                                                                                                 ;                                                             zw                                 _-'"

,,,. . ~..

g m; oE. . OFFICIALBUSINESS h

                                                                                                                                                                                                                                                                                                          " ^

_ , or -< " 2 - ^ e- M- &

                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                         . m%44 'i f
                              ,                                                                                                                                                                                                                                                    ~
                                                                                                                                                                           'J                                                                                                                                                                                        J '
                                                                                                                                                                                                                                                                                                                                                                                                                                                                                        ~

1, y- USE. 5300 ' C . - ] - l_ -^0

l'4 'yWrg - 42dPENALTf FOR :M -PftlVATE - 5,&[ l a - -

sw % ' . , W u'

                                .G~                                                                                                                                                                                                                                                                                                                                                                                                           ~ W 12G53515449s                                                                                                                                                  ,M                                                                                                                  ' ~*x '

- - - h US NRC-0CId; (1CylvA1xCI

                                                                                                                                                                                                                                                                                                                                 -                                                                          ~
                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                 # ' I'R, W                                                       '

$6 g, pgg Q, ' TPS-PDR-DIV-INrOhRh0N 2WFN-6E7 MANAGEMENT_F M '

                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                           ~
                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                  - 25 J
                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                      ~
                                 ,~ v .- %                                                                                                                                                                wa3y7997gN                                                                                                                                                                                                                                                                                                                   ,                          _

mn- -

                                                                                                                                                                                                                                                                                                                                                                     <.55"                                -
                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                             #                                                                     4 m - .
                                                                                    ,.m W                                  .
                                                                                                                                                                                                                                           ~
                                                                                                                                                                                                                                                                                                                                                                                     ~
                                                                                                                                                                                                                                                                                                                                                                                                                                    ,. .                                            e
                                                                                                                                                                                                                                                                .g                 ad       * =                                                                                                                                                                                                                                                     >,

r,_ -

• a - ; 3

                                                                                                                             'g     -%

_"" 2 'T Y - l r'__ .;f

                                                                 , .             '_2~                                                                                                    -,  .
                                                                                                                                                                                                                                                                                                                                       ~

w ?"': s' - - _,_ .c 'i

                                                                                                                                                                                                                 =~;--

Qd > , 3 "

                                                                                                                                                                                                                                                                                                                                                                                                                                                                                .                        ,._4-3,,
        ..,,2m.;.:.             +
                                                                                                                                                                                                                                                                                                                          -                                                  Td                     ~ b.               ._-                                                                     t                       ~ ~                                                         e
                                                                   . ~ . ,.                                                                                                                                             g ,. '                                                                                                                                                                                                      3                                         s                                                                                        .
                                                                                                                                                                                                 ;                                                                                                                                                                                                                      .mm p,                                                                           ,                                                                             s                 ~
                                                                                                                                                                                                                                                                                                 ,m. . . . .                   ,                             - :,,                                               _                                                                                                                                                                             .,
                                                          .I,,,                            F
                                                                                                                                                                                                                                                    ,f**:,.                                                                                                                                                                                         .n 1 -4

• IN-

                                                                                                                                                                                      -/.@                                                                                                                            _'v.,                                   r                                                                                        -
                                                                                                                                                                                                     .-   t -                                            e.                     . . , .
                                                                                                                                                                                                                                                                               'y;                 g_c                                    +
                                                                                                     ,q'                          .- ,-.                                                                                           .u,
                                                                                                                                                                                                                                                                                                    ",'                l
                                                                                                                                                                                                                                                                                                                            ~ "                     "
                                                                                                                                                                                                                                                                                                                                                                                                                                             ~Ds,,'         .g                                   ,                                                                          P ' ':                  L

a. ~

                                                                                                                                                                                                                                                                                                                                             , 7 .                                                                                  . ,

N " 8

                                                                                                                                                                                                                                                                                                                                                               -                 I                           ND ,,                                      ,q              __
                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                 +                          >j.     ; ' - '

jp't 'y ., ; ,

                                                                                                                                                                                                                                                                                                                                                          ~

v "~%'.' g ',.m. . 3

                                                                                                                                                                                   %_ g & ~ ~
                                                                                                                                                                                                                                 ~ 

s

                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                               ' F', , ,

3~ ^

                                                                                                                                                                                     - + -                                                                                       -

7._, 4 _'T - ..# ,3 , _ y., -

                                                                                                                                                                             /.

. _.2  ?%..c ,. .

a -^o '"

                                                                                     ._-                                                                                                                                                          f- p -                                            ,4:: s - +-

M , + a -- w . ~ r; a a + r g *k

                                                                                                                                                                                                                                                                                                 .'              .7,,
                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                             ,:x.,     n I. _
                                                                                                                                                                                            'g-7,_.-__
                                                                                                                                                                                                                                                                                                          .v

_r' l

                                                                                                                                                                                                                                                                                                                                                                                                                                 ~. n.3
                                                                                                                                                                                                                                                                                                                                                                                                                                                    ~-
                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                     -4 v

t 'l

                                                                                                                                                                                                          ,1;A i -                                                                    _N-_
                                                                                                                                                                                                                                                                                                          ~

L4.. *

• M"A ._. 3fj e

m

                                                                                                                                                                                                                                                                                                                                                                                                                    ._ue#.:-
                                                                                                                                                                                                                                                                                                                                                                                                                                  -                 ' . . , * ,.                                         =
                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                          . -                                                                            2
                                                                                                                                                                                       ..,                            o,p---
                                                                                                                                                                                                                                                           .* . .                                                                  -h-'

4

                                                                                                                                                                                                                                                                                                             '*- '                                                                                                                                                                             +

(

                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                  -]       ,
                                                                                                                                                                                                                           'Pf                                                                                                                                                                                                                                                                                                                                                                                                     -

[ ""'

                                                                                                                                                                                                                                                    -!=                                                                                                                                                                                                      . .                                                                _

ss-

                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                       .-l
                                                                                                                                                                                                                                                                                                                                     .-.                                                                                                                                                                                                                                                                                           ')     4
                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                          ]

J ~ _ ,. 1 79.m

                                                                                                                                                                                                                                                                                                                                                       ~
                                                                                                                                                                                                                                                                                                                                                                                                  ./*%,
                                                                                                                                                                                                                                                                                                                                                                                                           'N.                                                      3-
                                                                                                                                                                                                                                                                                                                                                                                           -e a-.

i

                              .3       1997 AEOD ANNUAL REPORT                         . NOVEMBER 1998 UNITED STATES                                                      FR9T CLASS MAR.

NUCLEAR REGULATORY CORMAISSION POSTAGE AND FEES PAID WASHINGTON, DC 20555-0001 PE w OFFK;1AL BUSINESS PENALTY FOR PRNATE USE,5300 120555154496 US 1 NDC-0CIO 1 A N IC yl va 1 xC 1 DIV-INrORMATION MANAGEMENT TPS-PDR-NUREG 2 11F N - 6 E 7 WASHINr+T2N DC  ?"555 1

                                                                                                       -}}