ML20148C689
| ML20148C689 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 09/19/1996 |
| From: | Lloyd R NRC |
| To: | Dale Yeilding NRC |
| Shared Package | |
| ML20148C622 | List: |
| References | |
| NUDOCS 9705270268 | |
| Download: ML20148C689 (65) | |
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From: Ron Lloyd To: DEY u' Date: 9/19/96 8:20am l
Subject:
Bob Christie contract Dale:
The total number of hours for Bob comes to 506 5. Total expenses come to $8545.01.
As we discussed earlier, the total number of hours exceed the total number of hours that were ;
initially projected for the task The reason for the over-run on the hours was the additional l work that was done as requested by Ellis Mershoff to provide PRA/ risk perspective insights i into team findings. l l
Any questiors. please call
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4 PROFESSIONAL EXPERIENCE SUS 131ARY C. 31. Stitchell Charles N1. (Chuck) Niitchell is a senior engineer with JBF Associates. Inc.. providing engineering support to the Nuclear Operations Analysis Center (NOAC). Str. 51itchell has 16 9ears commercial nuclear power experience involving reliability and risk assessment, operations assessment. systems engineering, startup testing power ascension testing, operations support, outage supervision. and component design. He received a B.S. degree in nuclear engineering from Pennsylvania State University.
At NOAC Nir. hiitchell has been involved with several projects regarding the assessment and evaluation of operating commercial nuclear power plants. He assisted with a trial program for assessing the effectiveness of using performance indicators based on event causes to assess the operating performance of nuclear power plants. He has been involved with numerous performance evaluations using the techniques developed in this trial program. Nir. Niitchell has managed and performed nuclear power plant licensee performance evalurtions for use by NRC diagnostic evaluation teams.
Previously. Nir. hiitchell held a variety of positions at several commercial nuclear power plants. As senior engineer with Stone & Webster. he was assigned to the engineering assurance audit task for the TVA Browns Ferry Design Baseline and VeriGeation Program responsible for technical and programmatic review of the i
complete design basis reconstruction. He verified con 6guration control and regulatory compliance within I the design basis documents. He evaluated licensing commitments, design criteria documents, test criteria.
and change control process.
While on assignment at Florida Power's Turkey Point plant, he specified quality documentation requirements for procurement of spare and replacement parts. He prepared nonconformance reports and performed root '
cause analyses and safety evaluations. As a staff member with JVS-Corporation, work at the San Onofre plant included participation in management prudency hearings for the plant and preparing studies of indu-try performance for plant startup durations during the period immediately following the TMI accident. Wh!!e on assignment to the Waterford Nuclear Station, Mr. Mitchell was a senior test engineer for the initial core load, low-power physics, and power ascension test program. He was responsible for directing on-shift testing.
analyzing test data, and preparing test reports for the licensee and the NRC.
Mr. Mitchell was previously with Combustion Engineering assigned as a senior test engineer to the Palo Verde Nuclear Station, coordinating test and maintenance activities on NSSS systems required for fuel load license, and preparing abnormal operating condition procedures. Responsibilities at Arkansas Nuclear One plant included coordinating containment building activities during refueling outages and supervising shift personnel during initial and reload test programs.
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b' i DALE F. NAWROCKI i Engineer VI i
i EDUCATION B.S. Chemacal Engineering, The University of Wisconsin-Madison { g i
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SUMMARY
OF EXPERIENCE i
1 Mr. Nawrocki has 4 years of experience in petrochemical plant process engineering and 5 years of experience in reAnery research and technical service. He has led hazard and operability l
(HAZOP) analysis and statistical quality control (SQC) teams, coordinated energy conssiva' ion and l
i environmental complisace projects, and routmely investigated day-tcxiay operational problems in PVC resin and ethylene production plants. He has an extensive background in computer modeling i and PC support (hardware and software) and traming. He led more than a dozen pilot i; nit evaluations of hydrotreatmg catalysu and feedstocks, and supplied technical support to refinery i
hydrotreaters. He also assisted in several large refinery integration feasibility studies, including hydrotreating, reforming, catalytic and thermal cracking, and H-Oil units.
I 1991 - Present Engineer VI, JBF Associates. Inc. Since joining JBFA in August 1991, Mr.
Nawrocki has helped debug version 2.1 of the 1.EADER* software and has assisted in HAZOP studies, including analyses of a refinery relief valve modification project, a water treatment project, a gasoline storage tank modification project, and a chlorine bleach plant. Helped develop and implement process safety management programs for paper mill clients.
Participated in and documented a process hazard analysis of an HF alkylation unit at a large refinery in which all issues of paragraph (e) of the OSHA PSM regulation (29 CFR 1910.119) were addressed.
1989 - 1991 ! ead Process Engineer, Vista Chemical Company, Oklahoma City, OK.
Responsible for process design and trouble-shooung in a PVC resin plant.
Add donal responsibilities included leading HAZOP studies and cw.Mg SQC and energy conservation projects.
1987 - 1989 Owner, Pioneer Floors and Interiors, an interior design and retail outlet in Buhl, Idaho, Was ==pamihla for all aspects of the business: scheduling,
=l====, two Anance, purchasing, advemalag, and sales. Employed two ofBee helpers, and four comrect workers. Averaged $400K annual sales.
1985 - 1987 Senior Chemical Engineer, T=hai~1 Services Section, Texaco Na+=1 Co.,
Port Arthur, Texas. Dunes included procesa engmeerms for the IJght Oleans Unit. Developed and tuned yield estimanns programs used to predict the economically optimal feedstate. Trained technical employees in the use of PCs.
DALE F. NAWROCKI Page 2 1980 - 1985 Chemical Engineer, Hydroprocessing Group, Texaco Port Arthur Research Laboratories. Duties included technical service to operating hydrotreaters and pilot unit evaluations of new feedstocks and catalysts, Was involved in several feasibility studies involving the integration of hydwur.4isg, reforining, catalytic and thermal cracking, and H-Oil units.
PROFESSIONAL TRAINING Hazard Evaluation: Qualitative Methods, Process Safety Institute,1991.
Hazard and Operability Analysis: HAZOP, Process Safety Institute,1991.
PUBLICATIONS AND REPORTS Review of Occurrence Repons involving irrndu1ted Nuclear Ekel Stomge from January 1990 through October 7,1993, ORNUNOAC 289, Oak Ridge National Laboratory, Nuclear Operations Analysis Center. Oak Ridge, TN, December 1993 (with J. A. Wheeler et al.).
Review of Occurrence Repons invoMng Irmdiated Matenal (Other Than fhel)from January 1990 through Oaober 7,1993, ORNUNOAC-288, Oak Ridge National Laboratory, Nuclear Operations Analysis Center, Oak Ridge, TN, November 1993 (with J. A. Wheeler et al.).
Review of Occurrence Repons Related to Component Aging for ihree DOE Idaho Fadildes:
Adunced Test Reacror, Idaho Genucal Pra:essing Plant, and Test Recaor Areafor the Period Septemoer 1,1991, thmuth September 13, 1993, ORNUNOAC-287, Oak Ridge National Laboratory, Nuclear Operauons Analysis Center, Oak Ridge, TN, October 1993 (with J. A.
Wheeler et al.).
Review of DOE Ste's Occurrence Repons Related to Component Aging fmm Seprember 1990 through July 1993 ORNUNOAC-285, Oak Ridge National Laboratory, Nuclear Operations Analysis Center, Oak Ridge, TN, September 1993 (with J. A; Wheeler et al.).
Users' Manualpr the Opemning E.xperience Assessment Cenrer Dasa Basepr DOE Occurrence Repont, ORNUNOAC-284, Oak Ridge Nadonal Laboratory, Nuclear Opersoons Analysis Cener, Oak Ridge, TN, hp.=hae 1993 (with J. A. Wheeler et al.).
Review of the las Alamar Nadonal Labomrory's occurrence Reponspr the Piusantsen Fv-:='-4 and Handung Fadlityptme July 1992 thmugh June 1993, ORNUNOAC-282, Oak Ridgn National Le-sgy, Nuclear Operations Analysis Center, . Oak Ridge, TN, August 1993 (with J. A.
Wheeler et al).
Review of the Los Alamos National Labomtory's Occurrence Repons for the Gemical and Merallurgy Research Fadlityfmm July 1992 thmugh June 1993, ORNUNOAC-281, Oak Ridge National Laboratory, Nuclear Operations Analysis Cemer, Oak Ridge, TN, July 1993 (with J. A.
Whoeier et al.).
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Review of Paducah Ste's Occurrence Repons fmm August 1990 thmugh April 1993, i ORNUNOAC-278, Oak Ridge National Laboratory, Nuclear Operations Analysis Center, Oak j Ridge, TN, June 1993 (with J. A. Wheeler et al.).
l Review of Oak Ridge National Labomrory Ste's Occurrence Repons for the High Flux Isotope Reaaor fmm January 1991 thmugh March 1993, ORNUNOAC-275. Oak Ridge National
- laboratory, Nuclear Operations Analysis Center, Oak Ridge, TN, May 1993 (with J. A. Wheeler et al.).
Review of the Pdersmouth Ste's Occurrence Reponsfmm Sepumber 1,1990, thmugh April 27, i 1993, ORNUNOAC-277, Oak Ridge National Laboratory, Nuclear Operations Analysis Center, 4
Oak Ridge, TN, May 1993 (with J. A. Wheeler et al.).
i Review of Savannah River Ste's Occurrence Regns, KReaaor, fmm August 1992 thmugh j January 1993, ORNUNOAC-274, Oak Ridge National Laboratory, Nuclear Operations Analysis
- Center, Oak Ridge, TN, April 1993 (with J. A. Wheeler et al.).
" Managing Safety: Do's and Dont's to ' OSHA-proof' Your Process Hazard Analyses," Osmical
- Engineenng, Vol.1, No. 3, March 1993 (with J. S. Arendt et al).
J A Process Harard Analysis of the Unit 30 Alkylation Unit, JBFA-213-92, JBF Associates, Inc.,
i Knoxville, TN, February 1993 (with C. M. Mitchell).
4 A Pmcess Harard Analysis of the Spent Caustic Tank at the Whiting Refinery, JBFA-167-92, JBF l Associates Inc., Knoxville, TN, July 1992 (with M. K. Merchant).
$ A Pmcess Safety Management Pmgram Planfor the Boise Cascade international Falls Mill, JBFA-241-02-91, JBF Associates Inc., Knoxville, TN, May 199" . (with M. W. Roberts and J. S.
! Atenat).
- A HAZOP Review of the internanonal Falls Mill CMonne Feed and Waste Gas Scrubbing S;' stems, i JBFA 24103-91, JBF Associates, Inc. Knoxville, TN, May 1992 (with J. R. O! vers).
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i A Pmcess Harant Analysis of the Raw water Pmita at she Odcago Re)lnery, J7s'A L.K-121-92, 4 JBF Associates, Inc., Knoxville, TN, May 1992 (with M. K. Merchant).
HAZOP Review Resader fkr Modficariant to she 37 Pipessill and SEU Relief Valve Systemt, JBFA LR 186-91, JBF Associates, Inc., Knoxville, TN, Deceinber 1991 (with M. P. Johnson).
! HAZOP Resuittfbr AKC Tank Farm Water Dmw Pmfect, JBFA-LR-193-91, JBF Associates Inc.,
i Knoxville, TN, Noveinber 1991 (with M. P. Johnson).
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PROFESSIONAL EXPERIENCE SU31 MARY J. J. Rooney James J. (Jim) Rooney is a Research Engineer with JBF Associates. Inc. He has 17-years experience in the safety, reliability, and risk assessment of nuclear power plants and chemical process plants. Mr. Rooney holds a B.S. Ch.E. from the University of Virginia and a master's degree in nuclear engineering and M.B.A.
from the University of Tennessee. He is currently rursuing a doctorate in industrial and systems engineering at the University of Alabama in Huntsville.
His most recent experience at the Nuclear Operations Analysis Center (NOAC) on the Sequence Coding and Search System (SCSS) includes reviewing and analyzing events at commercial nuclear power plants reported in licensee event reports (LERs) for the purpose of encoding this information into the SCSS data base and managing the QA program to ensure consistency of the data on SCSS. Mr. Rooney has also prepared reviews and summaries of LERs for the Ft. St. Vrain nuclear power plant. He previously developed a methodology for computer generated keywording of sequence-coded LERs. For a number of years at NOAC he abstracted and keyworded LERs for licensee nuclear power plants.
Mr. Rooney has managed the installation of reliability analysis computer software at customer sites in Canada. England, Japan. Norway, and the United States for JBF. He has also worked extensively in the areas of computer software and data base development including developing methodologies for dependent failure analysis, cause-consequence analysis, lines of assurance. and Good effects in nuclear power plants.
Mr. Rooney has managed fault tree analysis of suppon systems, aircraft crash hazards analysis and extemal events analysis in support of PRA projects for the Clinch River Breeder Reactor. He provided technical assistance to a dependent failure analysis of Arkansas Nuclear One and a Good analysis of Surry Nuclear Power Station Unit 1. He has also applied risk assessment techniques to numerous facilities in the Department of Energy's weapons complex.
Mr. Rooney is a registered Professional Engineer in the state of Tennessee. He is also an American Society for Quality Control (ASQC) Certified Quality Auditor Certined Quality Engineer, and Certified Reliability Engineer. He currently serves on ASQC's Board of Directors as Vice President of Section Affairs. l I
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SUMMARY
J. A. Farquharson John A. Farquharson is a systems engineer for JBF Associates. Inc. He has 15 years of experience in the nuclear industry, specializing in applying system engineering techniques to analyze the design. construction. !
l and operation of nuclear facilities. These techniques include reliabilitv. availability, and maintainabihty I (RAM) analyses. life cycle cost analy ses, and mechanical vibration analyses. j Mr. Farquharson's current responsibility as a contract employee at the Nuclear Operations Analysis Center (NOAC) is to review and analyze events at commercial nuclear power plants reported in licensee event reports for the purpose of encoding this information into the Sequence Coding and Search System (SCSS) i data base. He also has provided support in reviewing plant operating histories to support NRC Diagnostic I Evaluations. His responsibilities at JBF Associates involve performing and managing probabilistic risk I assessments of various Department of Energy systems and facilities. .
Prior to joining JBF Associates. Mr. Farquharson worked as a systems engineer on the Gas Centrifuge Enrichment Plant (GCEP) project. His primary responsibility was to perform RAM analyses of the centrifuge machine and the balance of plant equipment. As part of this responsibility, he prepared availability factors used to account for the impact of balance of plant system catages on plant throughput. In addition. Mr.
Farquharson managed a diagnostic development task which utilized centrifuge machine vibration data to predict and prevent machine failures.
i Earlier, at Bechtel Power Corporation Mr. Farquharson gathered. evaluated, and distributed nuclear power plant licensing information. This work emphasized review of balance-of-plant system design with respect to safety and conformance with NRC regulations. He also analyzed nuclear power plant radiation shielding configurations for safety impact using computer simulations. Mr. Farquharson spent an assignment at the Grand GulfNuclear Station construction site where he supervised and inspected the installation of mechanical instrumentation and related piping.
Mr. Farquharson has a B.S. in mechanical engineering and a master's in business administration from the University of Tennessee. Knoxville. He is a registered Professional Engineer in the state of Tennessee.
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PROFESSIONAL EXPERIENCE SU3151ARY L. E. Palko Leonard E. Palko is a systems engineer for JBF Associates. Inc.. providing engineering support to the Nuclear Operations Analysis Center (NOAC). hir. Palko holds a B.S. degree in nuclear engineering from the i University of Tennessee.
i Currently he is providing support at NOAC on the Sequence Coding and Search Sys:em (SCSS) data base for licensee event reports (LERs) reviewing the operating experience of commercial nuclear power plants and encoding the information. Additional responsibilities include providing on-call assistance to NRC/AEOD l.
j in performing special analyses and reviews of consistent operational issues and plant operating histories on
> a quick-turnaround basis.
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At NOAC Mr. Palko was involved in reviewing and clarifying unresolved safety issues to aid NRC in prioritizing these issues. The issues specifically being reviewed were spatial and functional system interactions occurring ddring selected accident sequences.
4 Previously he was involved in performing a Facility Risk Review of the h1ound Facility in hiiamisburg.OH.
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This work also involved performing several safety assessments of various systems at hfound. hit. Palko was 4 also involved in performing fault tree analyses to support the Gaseous Diffusion Plants Safety Analysis
- Report Upgrade Project.
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l l HENRIQUE M. PAULA Senior Engineer JI EDUCATION .
Ph.D. Nuclear Engineering, The University of Tennessee, Knoxville, Ten-
! g ((Course work and dissertation focused on systems reliability and assessment.)
M.S. Nuclear Engineering, Universidade c'e Sio Paulo, Sio Paulo, Brazil, g B.S. Electrical Engineering, instituto Nacional de Telecomunicas5es, Santa Rita do Sapucaf, Minas Gerais, Brazil, S
SUMMARY
OF EXPERIENCE Dr. Paula has 16 years of engineering experience, including 10 years performing probabilistic or quanutative risk assessment (PRA/QRA), process hazard analysis (PHA), hazard and operability (HAZOP) analysis, failure modes and effects analysis (FMEA), event tree analysis, fault tree analysis (FTA), quantitative external event (burricane, tornado, aircraft crash, etc.) analysis, and consequence analysis in the chemical, petrochemical, nuclear, defense, manufacturing, and mmin industries. Dr. Paula has written sections of Guidelines for Chemical Process Quantitativ Assessment, sponsored by the Center for Chemical Process Safety (CCPS) of the American Institute of Chemical Engineen (AIChE); Procedures for heanng Common Cause Failures in Safety and Reliability Studies, jointly sponsored by the Electric Power Research Instimte (EPRI) and the U.S. Nuclear Regulstory Commission (NRCh and Proceduresfor Conducting Probabilistic Safety Assessments for Nuclear Power Plants (Level 1), sponsored by the Inte;narionni Atomic Energy Agency (IAEA),
1991 - Present Senior Engineer II, JBF Associates, Inc. (JEFA) and Process Safety Institute Acu as a senior technical advisor and quality assurance engineer for (PSI).
JBFA projects. Performed these functions in risk assessments of a polyols reactor and a propylene oxide /teittary butyl alcohol (PO/TBA) oxidation unit.
Also acted as a consultant for the IAEA in the review of the PRAs for the Angra-1 NPP (Brazil, November 9-13,1992) and the Krako NPP (Slovema, May 20 24,1991).
Develops and teaches connes for PSI and AICHE. Also lectured for the IAEA on PRA mehod: aixi applications at the Paka NPP (Paks, Hungary, March 913,1992), Argonne National Laboratory (Argonne, IL, March 1988, March 1991, and January 1992), and Korea Atomic Energy Research Institute (Daeduk Danji, Taejon, Republic of Korea, December 24,1991).
I Developed Helps develop software for hazard analysis and risk assessment.
the mathemaucal specifications for BRAVO 2.08, a state of-the-art Vrtodows" program for performing event tree and fault tree analyses. Also developed
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1 i the technical specifications for QRA ROOTS *, a Windows" program for i 1991-Present (cont'd) storing, searching for, and retrieving equipment failure / repair data, human error probability, and external event (fire, flood, etc.) frequency. '
1987 - Present Project Manager, JBF Associates, Inc. Performs hazard evaluation, risk assessment, and reliability analysis for industnal customers. Acted as leader, or otherwise participated in the following studies: (1) a facility risk screemng study of a tissue mill, (2) the development of a process safety management (PSM) plan for a paper manufacturing company, (3) a PHA/HAZOP of a distillate hydrorrester, (4) an event tree / fault tree analysis to evaluate the frequency of violent cumene hydroperoxide (CHP) decomposition events at a phenol plant. (5) three plantwide PHAs/HAZOPs of polyethylene and polypropylene plants (6) FMEAs for electrical distribution systems at two large refmeries in the Gulf Coast, (7) a facility hazards review at a large copper mmmg company, including nuning, concentranng, smelting, refming, and electric power generation facilities, (8) facility risk review for an oil refmery's utility systems (e.g., powerhouse, electrical distnbution, water, steam, and plant air), (9) an FTA of fault-tolerant digital control systems.
r'annaian (10) an FTA of the 13.8 kV electrical distribution system at a refmery, (11) an external event analysis in suppon of a QRA to help the owners of a large chemical complex docule whether to expand an existing complex or build additional capacity in a new location, (12) an FTA of the carton fill systen.s ed the scoop drop systems at a large ===daeming plant, (13) a reilability, availability, and mai==iaahility (RAM) study of the Process Experimental Pilot Plant (PREPP) facility for processing low level transuramc co-amia='ad waste. (14) an FTA of two firewater supply systems at the Paducah Gaseous Diffusion Plant (PGDP), (15) an FTA to evaluate the frequency of criticality accidents involving the 10 MW high-assay freezer sublimers at PGDP, and (16) a ==%e FMEA of the lid closure machamie= for a cask specifically designed to transport r.dkieh waste.
1984 - 1987 Sysasos Engmeer, JBF Associates, Inc. Developed analysis motbods for the NRC, Sandia National Laboratones (SNL), Oak Ridge National I.abonnary (ORNL), and Idaho National Engmeenng i =ha==a y (INEL). Primded engemanns somces to SNL and to the NRC la the area of common cause falhus (CCF) analysis, and perfonned an uneartaimy analysis for the INEL regardag daily use of updated PRA/QRA infonnation Duties also incinded the development and application of methods for relating PRA infanmaske to NRC inspection ps.dww. generation of a dependen failure analysis phres guide, collection and analysis of dat=ad== falkue data, and collection and analysis of failures of nuclear reactor co=pana== caused by harsh environments. Developed awhade for applying PRA results to NRC inspection activities, and participated in the developmem of the Plant Risk computer Status Information Management System (PRISIM) program. Consultant to the International Atomic Energy Agency (IAEA)
i Page 3 HENRIQUE M. PAULA 1984 - 1987 during an international PRA conference held in Vienna, Austris, in June 1987. Performed a variety of tasks (plant systems analysis, data analysis, (cont'd)
CCF analysis, accident sequence analysis, and recovery analysis) in the review and update of the Arkansas Nuclear One - Unit 1, the Peach Bottom -
Unit 2, and the CONUS Demilitanzation Facilities PRAs.
1980 - 1983 Full-time graduate student at the University of Tennessee, Knoxville.
Tennessee. Held a teaching assisimmeip and supervised students suendmg a l
! computer-sided FORTRAN course.
1978 - 1979 Research Specialist. Instituto de Pesquisas Energdticas e Nucleares (IPEN),
Sio Paulo, Brazil Performed engineering analyses in support of IPEN's High-Temperature Gas Cooled Reactor (HTGR) experiments. Developed a methodology and a computer program to simulate the thermal response of '
IPEN's HTGR experimental facility. " Itis program evaluates several l
parameters, including the time necessary to perform the experiments. It was developed as a decision making tool for scheduling experiments and for allocating manpower.
PROFESSIONAL ACUVITIES Guest editor of s specialissue of the journal Reliability Engineering and 5)nem Sqfery, addressing the reliability performance, analysis, and evaluation of programmahle electronic systems (Vol. 39, 1993).
Methodsfor Calmwon of Mrc and Explosmn Na:ards (Traimng Course), AIChE, August 7-8, 1992.
Ha:ard and Operabluty Analysis (Training Course), Process Safety Instimte, Knoxville, TN, January 21 24, 1992.
Recipient of the Professunal Inlaianve AM, JBF Associates, Inc.,1984, and the Dedicated Service Aword, JBF Associates Inc.,1991.
Invited speaker at the Society of Fire Protection Engineers to discuss the use of risk mesman===
Oak Ridge, TN, January 10, 1991.
l U.S. pameipam in the IAEA's 3-year Coordinated Research Progmmme on Dam ^11* and l
Analysisfor Probabillrric Sqfery Analysis, held in Athens, Greece, February 1989, and in Vienna, l
! Austria, March 1988 Ind April 1990.
Certified Reliability Analyst, JBF Anociates, Inc.,1989.
Human Reliabiury in Engineered Systems Analysis (Tramag Course), JBF Associates,Inc.,1988.
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! HENRIQUE M. PAULA i
f PUBUCATIONS AND PRFRENTATIONS
" Analysis of Uncertainties in Interactive Probabilistic Safety Analysis (PSA) Models" Risk
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- Analysis, Vol.13, No. 2,1993 (with D. J. Campbell and V. H. Guthrie).
' Reliability Performance, Analysis, and Evaluation of Programmable Electronic Systems, with Emphasis in Chemical Process Applications" (Guest Editorial), Reliability Engineering and System Sefery, Vol. 39, 1993.
" Operational Failure Experience of Fault-Tolerant Digiul Control Systems,' Reliability ,
1 Engincenng and System Safety, Vol. 39,1993 (wi 5 M. W. Roberts and R. E. Battle).
' Failure Rates for Programmable Logic Controllers." Reliability Engming and System Safety, Vol. 39,1993.
Enhancements to Data Conection and Repomng of Single and Multiple Failure Events, NUREG/CR 5471 (SAND 89-2562), U.S. Nuclear Regulatory Comnussion. Washington, DC, March 1993 (with D. W. Whitehead et al.).
Proceduresfor Condamsg Probabiustic Safety Assessmentsfor Nuclear Power Plants (Level 1),
Safety Series No. 50-P-4, Intemational Atomic Energy Agency, Vienna, Austria,1992.
" Scheduling Updates of Probabilistic Risk Aasessments: De Arkansas Nuclear One-Unit 1 Experience," Risk Analysis, Vol.12 No. 2, June 1992 (with V. H. Guthrie and D. J. Fa%11).
Also published as ' Scheduling PRA Updates: The ANO 1 Experience," 7hmsacions of the Amencan Nuclear Society's 1991 Annual Meeting, held June 2-6.1991, in Orlando, FL. Vol. 63, the American Nuclear Society, Inc., La Grange Park, IL, June 1991.
" Qualitative Cause-Defense Matrices: Engineering Tools to Support the Analysis and Prevention of Common Cause Failures," Re#abi#ty Engineenng and System Sqfery, Vol. 34, No. 3,1991 i l
(with D. J. r=911 and D. M. Rasmuson).
' Data Needs for Common Cause Failure Analysis,' Pmceedings of the Internananal Corprrence on Probabi#ssic Sqfery Assessment and Management, held February 4-7,1991, at the University of California at Las Angeles, Beverty Hills, CA, published by Elsevier Scisnes Publishing Co.,
Inc., New York, NY, February 1991 (with G. W. Parry et al.).
' Analysis of Uncertainties Associated with the Numerical Rasuhs Evaluated by Imaractive Cc--+#onal PRA Models,' Proceedmgs of the Mrst inrenusional Symposamm on thu:ersainry Modeling and Analysis, held December 3-5,1990, at the University of Maryland, College Park, MD, published by IEEE Computer Society, Los Alamitos, CA 90720-1264, December 1990 (with D. J. Cm%ll and V. H. Guthrie). ,
l Page 5 HENRIQUE M. PAUI A
" Reliability Performance of Fault-Tolerant Digital Control Systems,' Plant /Opemrions Pmgress Vol.10. No. 2. April 1991 (with M. W. Roberts and R. E. Battle). Also published and presented l
in the following conferences:
l
. Proceedings of the Pmcess Contml Forum, sponsored by the Chemical Manufacturers
- Association, San Antonio, TX, April 1992.
Proceedings of the 24th AnnualIoss Prevention Symposium, AIChE, San Diego, CA.
August 1990.
. Third coordination meeting of the Intemational Atomic Energy Agency's Research Progmmme on Data Collecnon and Analysisfor PSA, Vienna, Austria, April 2 5,1990.
" Facility Risk Review as an Approach to Prioritizing Loss Prevention Efforts," Plant /Opemtions Pmgress, Vol. 9. No. 4 October 1990 (with M. L. Casada and J. Q. Kirkman). Also presented at the American Institute of Chemica! Engineers 1990 Spring National Meeting, Orlando, FL,
)
March 1990. I A Cause-Defense Appmach to the Understanding and Analysis of Common Cause Failures.
NUREG/CR-5460 (SAND 89-2368), U.S. Nuclear Regulatory Commanion, Washington, DC, March 1990 (with G. W. Parry).
- NRC Research in Common Cause Failures," Pmceedings of the U.S. Nuclear Regulatory Commission Sixteenth Water Reactor Safety Informanon Meeting, NUREGICP-0097, Vol.1, March 1989 (with D. B. Mitchell et al.).
" Data Base Features That Are Needed to Support Common Cause Failure Analysis and Prevention:
An Analyst's Perspective," Nuclear Safety, Vol. 31, No. 2, April-June 1990, also presented at the second coordination meeting of the international Atomic Energy Agency's Researth Pmgmmme on Dara Collection and Analysisfor PS4, Athens, Greece, February 13-17, 1989.
" Common Cause Failure Analysis," Section 3.3.1 (pages 221 through 237), GuideJines for c l Chemical Pmcess Quanntative Risk Analysis, published by the Camer for 'h==eal Process Safety of the American lasutute e' Chemical Engineers, New York, NY,1989.
l Procedures pr Deanng Common Cause Failures in Sqfery and ReitaMilty Sades (Vol 11:
Analyn'aal Backgmund and Techniques), NUREG/CR-4780, EPRI NP-5613, U.S. Nuclear Regulatory e'ammi.=ian, Washington, DC, and the Elecenc Power Rassamh Instans, Palo Alto, CA, January 1989 (with A. Mosleh et al.).
'A Probabilistic Dependent Failure Analysis of a D-C Electric Power System in a Nuclear Power Plant," Nuclear Sqfery, Vol. 29, No. 2, Apni June 1988.
User's Guide for PRISIM Arkansas Nuclear One - Unit 1, Vol.1: Pmgram for inspeacts, NUREG/CR 5021 (ORN11TM 10604), U.S. Nuclear Regulatory Comminion Washington, DC, March 1988 (with D. J. r@ll et al.).
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! HENRIQUE M. PAULA Page 6 4
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User's Guide for PRISIM Arkansas Nuclear One - Unit 1. Vol. 2: Pmgmm for Regulators. l NUREG/CR-5021 (ORNI./TM-10604), U.S. Nuclear Regulatory Comm'uion, Washington, DC, j; Wrch 1988 (with D. J. Campbell et al.). i
. "An Overview ot'the NRC/EPRI Common Cause Analysis Framework,' Pmceedings of the U.S.
Mscinar Regulatory Commission Rfteenth Water Reacror Safety Meeting, NUREG/CP 0091, 1 February 1988 (with D. M. Rasmuson et al.).
5 Procedures for 1>eanng Common Cause Failures in Safety and Reliability Studies (Vol. I:
! Pmeedural Fmmework and Examples), NUREG/CR-4780, EPRI NP-5613, U.S. Nuclear i
Regulatory Commission, Washington, DC, and the Electric Power Research Institute, Palo Alto.
CA, January 1988 (with A. Mosleh et al.).
) "A Restructured Approach to the Partial Beta Factor Method" (unpublished paper), JBF Associates, Inc., Knoxville, TN, October 1986. ,
4 Risk Assessment Applicanon to NRC Inspection Progress Reportfor the Period January 1985 to 4
January 1986, NUREG/CR-4560, U.S. Nuclear Regulatory Comminion, Washington, DC, June l 1986 (with D. J. Campbell et al.).
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- "Leuer to the Editor
- Comments on 'On the Analysis of Dependent Failures in Risk Assessment i and Reliability Evaluation' in Vol. 26, No. 3," Nuclear Safety, Vol. 27, No. 2, April-June 1986.
! "A Methodology for a Time-Dependent Analysis of Accident Sequences and Complex Reactor
- Systems," Ph.D. dissertation, the Univenity of Ten =u*, Knoxville, TN, December 1984.
j "Desenvolvimento de Modelo de Simulaqio de Transientes Termicos no Circulador de Hdilo do CNEN" (in Portuguese), master's thesis, Insututo de Pesquisas Energdticas e Nucleares,
- Universidade de Sio Paulo, Sio Paulo, Brazil,1979.
$ REPORTS
. Facility Risk Screening Study of the Crisoba IIssue Mill at Emy de Morelos Edo. de Mir,
. JBFA-112-93, JBF Amanime==, Inc., Knoxville, TN, May 1993 (with F. Grimaldi et al.).
A Pmcess Haaard Analysis of the Dissillare ltjeu..uer (DRT) at 9seil Oil's Wood River i %W--g Compter, JBFA-30692, JBF Associates, Inc., Knoxville, 'IN, May 1993 (with D. B. Wright).
1 State of the Art of Level 1 FM Methodology, NEA/CSNI/R(92)18 (Restricted), Nuclear Energy Agency, Issy-les Mouline:ax, France, January 1993.
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HENRIQUE M. FAULA Page 7 A Pmcess Safety Management implementation Planfor Southeast Paper Manufacrunng Computy, JBFA-266 92, JBF Associates, Inc., Knoxville, TN, January 1993 (with W. G. Bridges).
BRA VO 2.08 Technical Reference, JBF, Associates, Inc., Knoxville, TN, January 1993. l BRAVO 2.0. ReHability, Awxilability, and MaintamabiUty (RAM) Analysis and Risk Assessment 1 Sofbare, JBFA-110-92, JBF Associates, Inc., Knoxville, TN, January 1993 (with V. H. Guthrie et al.).
A Process Hazard Analysis of the HAC Project (kiC-1024)for the Polypropylene Plant at Phillip's Houston Chemical Compte.x, JBFA-130-92 (Vols. I and 2), JBF Associates, Inc., Knoxville, TN, November 1992 (with M. C. Coker, Jr.).
A Process Hazard Analysis of the Polypropylene Plant at Phillips 66 Company's Houston Chemical Comples. JBFA-142 91, January 1992 (with J. Q. Kirkman and D. L. Machiela).
A Pmcess Hazard Analysis of the Devewpmental Plant at the Houston Chemical Comple.x, IBFA 13191, September 1991 (with J. Q. Kirkman and R. L. Brune).
Fault het Analysis of Pmeter and Gamble's Scoop Dmp System at the Augusta Plant, JBFA 105-91, JBF Associates, Inc., Knoxville, TN, March 1991.
A Fa!!ure Modes and Efects Analysis of the Pmposed East /Centml Electrical Load Center No. 39 at Amoco's Te.zar City Refinery, JBFA-134-90, JBF Associates, Inc., Knoxville, TN, December 1990.
A Quantuative Risk Assessment of the . . . Phenol Plant . . . (Confidennal Client), JBFA-117 90, (Vols.1 and 2), JBF Associates. Inc., Knoxville, TN, August 1990 (with M. F. Johnson and T. J. Abrahamh
. Reliability, Anallabiusy, and Mantamability Assessment of the PREPP Facility, JBFA-11,1-90, JBF Associates, Inc., Knoxville, TN, July 1990 (with V. H. Guthrie et al.).
ReliabiUty Analysis of Undergmund Mre Water Piping at the Paducah Gaseous DIBksion Plant, JBFA-101-89 (Vols.1, 2, and 3), JBF Associates, Inc., Knarville, TN, January 1990 (with D. J. r *H et al.).
A Reuabinty Analysis of the Preuminary Design of the WEDGE-LOC *11d C2asure Mechanisnrfor the NAC Combined Dunsport Cask, JBFA-LR-106-89, IBF Associanas, Inc., Knarvills, TN, October 1989 (with J. S. Arendt et al.).
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Page 8 HENRIQUE M. PAULA I
i' A Frequency Assessment of the Criticality Design Basis Accidentsfor PICS 10 MW High-Assay Freezer /Sublimers, JBFA-117-89, JBF Anociates, Inc., Knoxville, TN, August 1989 (with j i
! J. R. Kitchner). l 1
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- Hydrocarbon Flare System Gallenges Caused by Failures in the J3.8 KV ElectricalDistnbmion
- System, JBFA-Il4-89, JBF Associates, Inc., Knoxville, TN, July 1989 (with J. Q. Kirkman etal.).
Fault Tree Analysis ofFault-Tolerant Digital Control System Architectures, JBFA-LR-105-89, JBF l Associates, Inc., Knoxville TN, June 1989.
t l Facility Hazards Review of the Kennecott Utah Copper Facility, IBFA-109-89, JBF Associates, Inc., Knoxville, TN, April 1989 (with M. L. Casada).
9 ting Risk Analysis for the Houston Chemical Complex, IBFA-102 89, IBF Associates. Inc.,
- Knoxville, TN, March 1989 (with D. J. Campbell et al.).
Facility Risk Review of the Suncor Tar Island Facility, JBFA-122 88, JBF Associates, Inc.,
! Knoxville, TN, October 1988 (with M. L. Casada and J. Q. Kirkman).
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! Risk Management Program Planfor Mound, JBFA-120 88, JBF Associates, Inc., Knoxville, TN,
! September 1988 (with D. J. Campbell et al.).
1 Task 5 Draft Report: A Cause-Defense Methodologyfor Common Cause Failure Analysis, JBFA-
! 116 88, JBF Associates, Inc., Knoxville, TN, August 1988 (with D. J. Campoell).
+ RAM Applicanon Study for the Proposed Waste Management System, JBFA-LR-104-SS, JBF 4
Associates Inc., Knoxville, TN, July 1988 (with V. H. Guthne and J. A. Fasrpharana).
i Analysis of the Unceranndes in the Sgmpeance Factors Displayed in PRIslM, IBFA-101-SS, IBF Associates, Inc., Knoxville, TN, February 1988 (with D. J. c=911 and V. H. Guthrie).
Reduenng the Costs of Producmg and Updanng PRISM CongarerP' rograms, IBFA-124-87, JBF Associates, in;:., Knoxville, TN, December 1987 (with V. H. Guthris et al.).
i Scheduling PRA Updatest 7he ANO J Experience, JBFA-113-87, JBF a aah,Inc., Knoxville,
- TN, October 1987 (with D. J. r=@ll and V. H. Guthris).
4 Dependent failure Analysis Procedures Guide, JBFA 109-86, JBF Associates, Inc., Knoxville, TN, October 1986 (with D. J. Campbell and J. R. Khthner).
Risk Assessment Application to NRC Inspection 'nterim Progress Report, IBFA-106-S$, IBF l~
Associates, Inc., Knoxville, TN, December 1985 (with D. J. C=== hall et al.).
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Page 9 HENRIQUE M. PAULA i
Reladng PRA Informanon to inspecnon Modules, JBFA LR-l12 85, IBF Associatea, Inc.,
l Knoxville, TN, September 1985 (with D. J. Campbell and V. H. Guthrie). l 4
Analysis of Dependent Failure Events and Failure Events Caused by Hr.rsh Eavsronmental Condidons, JBFA-LR-Ill-85, JBF Associates, Inc., Knoxville, TN, August 1985 (with D. J. Campbell).
Demonstmtion /pplication for the Dependent Failure Analysis Procedures - Computer Applications, JBF Associates, Inc., Knoxville, TN, June 1985 (with J. J. Rooney et al.).
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A Survey ofS. Factor and C Faaor Applications. JBFA-LR-104-84, JBF Associates, Inc., \
- l Knoxville, TN, September 1984 (with D. F. Montague).
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PROFESSIONAL EXPERIENCE SUhth1ARY W. P. Poore Willis P. (hiike) Poore has been on the staff of Oak Ridge National Laboratory (ORNL) for 16 years, with 14 years of experience at the Nuclear Operations Analysis Center (NOAC) at ORNL. His experience includes the evaluation and assessment of commercial light-water reactor operating experience. the development and interpretation of commercial nuclear power plant performance indicators, and the assessment of the adequac) of bulk power system reliability.
Afr. Poore holds B.S. and bl.S. degrees in nuclear engineering from the University of Tennessee. He is a registered engineer in the state of Tennessee and has attended NRC training courses on BWR systems.
hir. Poore is currently the manager for four NRC projects:
- 1. Sequence Coding and Search System (SCSS) Database Operation. He manages the work to encode data from licensee event reports (LERs) into the SCSS event tree structured format which permits detailed retrieval on individual component or system failures, personnel errors, or on combinations of same occurring during the event. Sir. Poore was responsible for the development and implementation of system descriptions, code descriptions, and quality assurance and control practices to help ensure the accuracy and consistency of the 40,000 LERs currently on the SCSS database.
- 2. SCSS Database Utilization. Sir. Poore manages the efforts of several NOAC staff members who provide an interface between large numbers of users from NRC offices (RES. NRR, AEOD, as well as regional offices) and the resource of operating experience contained in the SCSS and helps them in identifying and resolving safety-related issues.
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- 3. SCSS Database Development. Sir. Poore manages efforts to provide updates and enhancements to I the SCSS database. Recent enhancements resulted from (a) implementing a major revision to the database management software on the mainframe, (b) moving the database management system to a more powerful computer which replaced aging hardware. and (c) investigating alternative platforms I (i.e., workstations) for operating the database.
- 4. Operational Event Analysis for Programmatic Performance Indicators. He provides technical assistance to AEOD in the development and implementation of performance indicators including causes for each event and corrective actions taken by the licensee for addressing problems and deficiencies.
Prior to joining the NOAC staff, hir. Poore was responsible for preparing a utility maintenance scheduling procedure for a Department of Energy study addressing the adequacy of the reliability of the nation's bulk power system. hir. Poore also developed the interface between the reliability parameters developed at ORNL and the effects parameters developed by subcontractors to evaluate the consequences of decreasing reliability l levels. Previously, hir. Poore utilized data from two pressurized water reactors to develop an improved
- l. methodology for applying in-situ methods for calculating resistance temperature detector (RTD) response i
times.
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1 Resume of DANIEL T. CANNON EXECUTIVE
SUMMARY
- l Over 25-years experience in the computer hard,vare, soAware, services, and manufacturing industries, with emphasis en datah==e and Web develnement using client server and Microsoft technalogies. These technalogies i include Windows NT Saver, Windows NT Warh*=*iaa Windows 95, MS-SQL Server, Transact SQL, Internet i Informatum Server, HTML, Internet Database Connector, and Powerbuilder. My technical expertise and broad )
practical experience are combined with excellent analytical, abstraction, and simplificauon skills to design and construct flexible, scalable systems that are easy to use and match client requirements and expectations. My organization, communicadon, and presentadon skills result in effective, focused, and easy to understand presentations, technical dar'==aats, and proposals -
Hardware: Intel based systems, Digital Equipment Corporadon (DEC) VAX, and DEC PDP-1 I systems Software: Windows NT Server, NT Workstation, Windows 3.1, Windows 95, MS Internet Information Server (IIS), MS Internet Database Connector (IDC), HTMI/Naese=WInternet Explorer, MS Front Page, Powerbuilder, Windows SDK, Visual Basic, Microsoft SQL Server, Sybase SQL Server, Infornux, ERwin CASE Tool, IEW/Knowledgeware, IEF/ Texas Instruments, dBASE IV, FoxPro, Access, FORTRAN, COBOL, and ==ncious finaamal and personal productivity software.
EDUCATION:
B.E. Industrial Engmeermg,h oungstown State University L' Accounting Major,3 years, O o tate L'aiversity Other Trauung- I Microsoft Windows NT Server-MS Trammg Systems i Informadon Engmeermg Workbench (IEW)-CEC, Ltd. 1 Informadon Engmeermg Facility-Texas Instruments Meridian SL-100 digital voice / data switch-Northern Telecom Data communicadons and networking /the OSI model-The Leammg Tree, Inc.
VAX/RSX/DCL trammg sessions-Digital Equipment Corporation :
Effective Negotiating-Karass Semmars EXPERIENCE:
Technical Task T >=dar Martm Manetta Energy Systems 1992-Present Provide tarknie=1 and adminientive direction to project staffin the life cycle development ofinformadon systems for chents in the public sector. Analyze, ddgn, and build client server applications with emphasis on database
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and Web applicadons. Functions performed include NT Server /Domam admmistration, Web Admimstradon, database administration, Web /SQL-Server /NT security admmistradon (within the Lockheed-Martin enterprise network using a centralized NT security domam architecture), Web Authonng, IDC/HTX script development, database design and construction, Transact SQL procedure development, Powerbuilder client software development, and Powerbuilder object admmistradon.
Past responsibilides include leading a technical team which provided support to the Veterans Benefits
. Administration (VBA) in defining and assessing system architectures for use in a major VBA modermrarion effort, including (1) analysis of SQL based, distributed, reladonal DBMSs for use in mission crideal, large scale applications; (2) identification and assessment of mamframe, client-server, and massively parallel technologies; and (3) identification and assessment of operating system software and utilides Program Manager The MAXIMA Corporation 1988-1992
. Administrative and technical manager for $7 million contract to provide support services to Martin Marietta Energy Systems in the life cycle development of informe. ion systems. Interfaced with government and wwdal clients in planrung and functions associated with contract admmistration. Provided consultation and direction to clients, technical staff, and others in the applicadon of Information Engmeenng methodology, Computer Aided Software Engmeenng (CASE) tools, relational database technology, fourth generation languages, and other software development utilides.
I Under sponsorship of the U.S. Army Aviadon Systems C-M led the software design team in formulating ;
fundamental architectures and prototype developmmt of the Predictive Aircraft Maintenaner System (PAMS) for the Apache and Blackhawk helicopters. Under sponsorship of the Hazardous Waste and Reinadial Action Program (HAZWRAP), led the life cycle development effort for the Planning, Budget, and Control system developed for the Environmental Restoration and Waste Management program, an assistant secretary level l orgamzation within the U.S. Department of Energy.
President / Owner !
System Source Computer Center, Authonzed DEC (Digital Equipment Corporation) Re Seller 1982-1988 Managed the financmg, construction, start-up, and staffing of System Source Computer Center. Managed admmistrative and eachnical operations Designed, configured, installed, and impl-*M turnkey solutions utdizmg DEC hardware, intelligent workstations (DEC,1BM, Apple, etc.), DEC operstmg systems and layered products, taird-party system / application software, fourth generation development tools, and in-house tanknical cupertise. Plannad and m deeffective demonstrations and training sessions. Provided direction and support i to technical personnel. Provided consultadon in the areas of financial structure and accounting procedures to customers. Tramed pers d and developed utilities to anhaner the M16*iaa of resources in an integrated environment. Analyzed customer needs and prepared complete turnkey proposals.
l Designed data structures, procedures, and program logic using relatv=al data base technologies, fourth generanon ,
f languages, system utilities, and other layered products in the develaa aa=* and implamantarian of end-user specific, custom applications. Knowledge of DCL and DEC layered products in both the PDP 11 (RSX) and VAX(VMS)envummmte Also utihzed IBM 360/370 (MVS & JCL), IBM, and Apple PC's, several high level languages, and fourth generation development tools. Provided system level and application support of both in-house and end user systems 1 , _
. ~ . , _ _ . . ._-- - .. . . .- - - . - . . -
dga Mananer/ Project Manager Republic Steel Corporation 1977-1982 Responsible for the promotion, sale, administration. coordinadon. and management of project oriented, engmected products to govemment agencies, large highway contractors, dealers, and political subdivisions in four Southeastern states. Developed strong customer reladonships and increased sales in the district from
$650,000.00 tojust under $3 million. Isxi the Division and Southern Region in dollar volume sales in 1981 and 1982, during which time there was a generally declining demt.nd for the company's product.
Plant Manager Youngstown Steel & Alloy Corporation 1973-1977
. Hired by new ownen for full responsibility of plant operations and the supen'ision of 30-40 people to assist in a successful transition of the +4 ion to a profitable status. Analyzed, designed, and implemented automated inventory control, billing, accounu receivable, and cost reporting systems implemented on NCR computer systems. Assisted in formulation of 5 year Business Plan and preparadon of annual budgets. Formulated and implemented manufacturing policies. Developed, coordmated, and =A =;ai tered programs to meet company objectives. Defined and established standards of performance, implemented scheduling / production procedures, and raised employee morale by providing incentives, improving workmg conditions, and msurmg open communicarians Productivity was dramadcally improved, along with employee attitudes. In addition, through extensive plant / grounds refurbishment efforts and community involvement, the company was recogmzad as a progressive leader in I,he local economic area.
S=lae Fnein-/Proiect Manneer Syro Steel Corporation 1969-1973 Responsible for estunating, proposal preparadon, sales / customer support, and project management of construction related, engineered products sold to government agencies, large contractors, and dealers. Also promoted and demonstrated these products to federal agencies, state highway departments, and other design groups.
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i ROBERT F. CHRISTIE Overall Experience l
Founder and soh. proprietor of Performance Technology, an engineermg canaking fhm specializing in reliability engineenng, probabilistic risk assessment, and safety analysis. Mahn 1994 to present.
Cofounder and partner of Reliability And Performance Aemmen (RAPA), an engmrsaring consulting firm. June 1989 to October 1994.
)
Nuclear Engineer Tennessee Valley Authority. January 1974 to June 1989. l Principal areas of experience:
Reliability / Availability Engmeenng for Coal and Nuclear Plants Probabilistic Risk A====at for Nuclear Plants Reliability Centend Maintenance for Nuclear Plants nermal-Hydraulic Analysis for Nuclear Plants Containment Analysis for Nuclear Plants Safety System Analysis for Nuclear Plants .
HVAC and Environmental Control Recent Experience High Flur Inntape Rasrear - RaHahility C x=M M;* = = N _ __ _
Started in August 1992 to develop and implammar a Raliability Ccatered Mainaa===r*
Program for the High Flux Isotope Reactor at the Oak Ridge Natmaal Laboratory. This program is based on the System Reliabdity Program at the River Bend Station. Work camplanad bdoes neenh~
1994 has included analysis of the pa system, the emessency dassel generaanrs, and -%
Instranentation and Controls, na intent of the program is to improve the performance of cruical systems at the Reactor and have a living program to monitor the impeuvemane. A uniSed data collection program was also defined to enable HFIR personnel to updase all analyses in a cost effecove manner making the manmum use of existing infortnanan programs.
De RCM Program was placed on hold fmm MM 19944hrough Sepa==han-1995 due to the dissoludon of the firm Reliability And Performance A<=a< == ne RCM Program asHFR was
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restaned in September 1995 to include at ! cast 16 " systems" and a comprehensive analysis of these '
j systems along the lines of the pressunzer system and the emergency daesel generators. Pr=limi=*'y computer rnodels have been developed for six of the systems and a computer program has been generated to assist the Shift Techmcal Advisors in the collecnon of data.
Fersni 2 Nucl==- Ptmat Svetem Relfahility Pros emm I From February 1995 through September 1995, assisted Fernu 2 personnel in the initial development of a System Ralsability Program to help in the implementation of 10 CFR 50.65, Maintenance Monitonog Rule. Main emphasis was to assist in the development of performance criteria and monitoring programs for use by the system engmeers in implementing the Maintenance Monitonng Rule.
a i Artraname Nuclear One - System RelishiHtv Pm. -
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l Starung ir. September 1992, assisted Arkansas Nuclear One . Unit 2 pm.c,anel in the
' performance of the Venfication and Validation effon of the draft guidelines generased by NUMARC in response to 10CFR50.65. Maintenance Monitoring Rule. When this effort was completed in i
December 1992, started to implement a System Reliability Program at Unit I and Unit 2.
3 Work completed at ANO has included analysis for the following systems at Unit 2 Emergency Feedwater, Diesel Generators Chenucal and Volume Control. Feedwater/Condenaar*
4 Service Water. Feedwater Control. EIecuo-Hydraulic Control The system analyses for Urur 2 were also unlized in the Unit 2 Probabilistic Risk Assessment to desanmne a time Q=*- core damage frequency. Analyses were completed on the Diesel Oenerator. E-- .-y Feedwaser. Makaap and Punf2 anon systems at Unit 1. The system analyses for the Diesel Generators and the Eu .--.y Feedwater System were utilized in the Unit 1 Probabilistic Risk Anramant to determine a tune dependent core damage frequency. Ultimate objeenve is to have a living program that will be used
- by various site organi7arions to monitor and improve system and plant performance in a cost j effecuve fashion.
Adve==4 N neenn Source n ,ene . Maine n.=~ rnen. _v-=
Starung in May 1993, became a mernber of a team of engmeers from vanons organitarians assisting ANS personnel at the Oak Ridge National Labc-seiy with integratmg mamtenance j concerns into the design of the Advanced Neutron Source Reactor. Scope of work also includes assisting ANS personnel in the fields of Reliability, Av.a.hmry, and Maintamabdity. Warit on De Advanr>rogram findings to the NRC.
Mr. Belles also provides technical support to the Department of Energy (DOE) in the analysis of data for the DOE Performance Indicator (PI) Program. This pre:ect includes review of department data sources.
development and maintenance of the P! Program data base, preparation of PI trending reports for submittal to the Secretary of Energy, and development of training materials for the training of DOE and DOE contractor personnel on program requirements.
Prior to joining ORNL, Mr. Belles was employed by Florida Power and Light and held an active senior 1 reactor operator license to' operate the Turkey Point nuclear power plant. Mr. Belles was an on-shift watch J engineer, responsible for the supervision of the on-shift licensed and nonlicensed operators. He ensured the t
o p an-ofhd i
. appropriate manpower was directed toward successful completion fl t e- ay tas ks, equ pmen clearance orders and plant work order support. Mr. Belles also previously worked for Sonalyst's Inc. as a ]'
senior analyst. He analyzed results of submarine security exercises for trends in submarine detection as part of the ballistic missile submarine security program. Mr. Belles interfaced directly with civilian and navy program personnel and produced an annual submarine detection report for Congress. i l
and received a B.S. degree in Mr. Belles graduated with distinction from the U.Syaval Academy i '
systems engineering. He subsequently graduated in%from the Navy Nuclear Power School. Mr. Belles spent eight years on active duty in the submarine service. He is currently matriculating in a graduate program in engineering management.
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JAMES L. HARDEE l l
PROFESSIONAL EXPERIENCE Primary areas of interest and experience:
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- Network database architecture design, implementation and administration using Microsoft Windows 95, Windows NT Workstation, Windows NT Advanced Server, Access, and SQL Server.
- Data resource management and database application development.
- Organizational and social aspects of computer systems development.
- The role of repository technology for information resource sharing within large organizations
- ' Implementation of information resource mana ;ement (IRM) and data administration programs.
- Strategic information systems planning.
- Ilusiness modeling for strategic data planning and IRM.
- Theory and methods for systems analysis.
Major Projects as Computing Specialist,1984 to present. Martin Marietta Energy Systems Inc.,
(Oak Ridge National Laboratory, Energy Division, 1984-1990; Advanced Technology Organization, Data Systems Research and Development Division,1990-Present).
Oak Ridge National Laboratory Compliance Assurance Program (CAP). Work with the Program Manager to develop the Standards / Requirements Identification Document (S/ RID) database of environmental, safety, and health requirements and assessment results. Develop database applications for CAP staff and end-users using Microsoft Access. Design, install, and administer CAP office network to connect staff and end-users to compliance assurance data and database applications. The office network consists of a Microsoft Windows NT Advanced Server with Windows NT Workstation, Windows 95 and Windows 3.1 clients. (1994 - Present)
CINC's Decision Support System for United States Transportation Command. Oracle 7 database external systems interface design. Oracle 7 installation on Sun Sparc workstation.
Installation of Oracle SQLnet and Oracle client applications (1993-1995)
Office of the Deputy Chief of Staff for Operations and Plans (ODCSOPS) Integrated Database Assessment. Worked with a team of specialists to review a third-party database system development proposal and provide critical evaluations and recommendations. Sponsor's praise of the team's effort resulted in special recognition of the team members. (1994) l Waste Management Support Network. Developed a PC network and remote access (PC dial-in) interface for the Tennessee Department of Environmental Control to access Energy Systems Waste Management Organizations's (ESWMO) Central Waste Tracking System l (CWTS)...(1993-1994)
National Sample Management and Tracking System. Facilitated interaction of local environmental sample management and tracking offices across the US with the Department of
1 e Energy's Laboratory Management Division to identify requirements for sharing sample rnanagement and tracking data nationwide. Developed project strategies. Developed data and applications models to support local and national objectives. Led sample management tracking system prototype development team. (1992-1993) 1 Military Airlift Command Information Resource Management System (MIRMS), Led MIRMS concept development and requirements definition, organized support for MAC data administration implementation, and as deputy projec'. manager, was responsible for project planning and managing subcontractor personnel. (1990-1992)
Major Projects as Computing and Database Consultant,1992 to Present. (Self Employed)
Patient Information and Billing System. Client: Serene Manor Medical Center, Rita Kidd, Administrator. Developed specialized accounts receivable system to handle complex Medicaid reimbursement calculations and reporting requirements.
MED-Axxess System Development. Client: Mountain Laurel Corporation. Mary Lee Evers, President. Worked with members of Mountain Laurel Corporation to develop cost control and inventory management database and applications to support the new practice of in-office surgery.
EDUCATION Degree: Bachelor of Science, Physics, University of South Carolina, @
Continuing Education: University of Tennessee graduate study in Industrial Engineering and Management. Subject areas include:
- Organizational Theory and Behavior o Engineering Marketing l e Strategic Management of Technology and Innovation e International Communications Professional Training: Administer the Oracle 7 Database (1994) Oracle Corporation.
Administer the Oracle 7 with the Distributed Option (1994) Oracle Corporation.
Develon Anplications with the Distributed Option (1994) Oracle Corporation.
Orcani7ational Systems Desian Designina Hich-Performance Organivations -
(1992) OSD Alliance New Management Tools - (1992) Conference of Organizational Systems Designers by Joe Colletti of GOAL /QPC.
Information Fnaineering - (1992) Clive Finkelstein Relational Database Design - (1991) by Paul Winsberg for Sybase Education.
Recositorv Management System Training - (1991) InfoSpan Corporation.
All About IRM -(1989 through 1991) Barnett Data Systems.
James Martin's World Seminar - (1990) Technology Transfer Institute.
l Structured analysis. Structured Design -(1989) Garant and Associates.
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Decision Cornoutine Stratecies. Technc'acies. and Practice -(1986)
Technology Transfer Institute.
Structured Analysis (Yourdon/D.: Marco) - (1985) Lawrence Livermore National Laboratory.
Knowledce Encineerine - (1985) Teknowledge, Inc.
Artificial Intellicence - (1984) ORNL.
- . PUBLICATIONS M. R. Cossey, et al., " Office of the Deputy Chief of Staff for Operations and Plans (ODCSOPS)
Integrated Database Assessment," September,1993.
l' J. L Hardee, et al., " Energy Systems Waste Management Organization Waste Management Suppon ,
Network High-level System Design Addendum for the PC Network Interface," January,1994. j J. L. Hardee, et al., " Implementation Plan to Suppon DOE LMD's Near-term National Office of l Sample Management Strategy,". October.1992.
' J. L. Hardee, et al., " Local Sample Management and Tracking System Prototype Requirements l
l Document," October,1992.
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J. L . Hardee and S. H. Huff, " Distributed Data Dictionary Analysis and Prototypbg Results," May L
l 1992. Client / server data dictionary prototyping analysis and recommendations sponsored by the l Military Airlift Command and the Air Force.
A.'H. Voelker and J. L. Hardee, " Revitalizing Synthesis in the Systems Development Process,"
! October,1990. Working Draft.
l A. H. Voelker and J. L. Hardee, " Implementing IRM: Liraits of the Rational Model," May 1990. l Working Paper.
J, L. Hardee, J. L. Christian, " Strategic Systems Team Organization Manual," April 1990. Working Draft.
l K. D. Streetman, et al., " Issues and Approaches for Electronic Document Approval and Transmittal
! .Using Digital Signatures and Text Authentication," Manin Marietta EnergySystems, Inc., Data j Systems Engineering Organization, Data Systems Research and Development Program February 1989.
J. L. Hardee, " Vitalizing Program Planning with Automated Project Management Feedback,"
November 1988. Unpublished working paper. .
I j
J. L. Hardee and A. H. Voelker, "Why Computer Systems are So Difficult to Build," Proceedings of the Twenty-Founh Annual Meeting of the Institute of Management Sciences, Southeastern Chapter, 3
Myrtle Beach, South Carohaa, October 1988.
J. L. Hardee, "Uses of the Business Model to Meet the Needs of Functional Managers," Proceedings of j the Twenty-Third Annual Meeting of the Institute of Management Sciences, Southeastern Chapter, Myrtle Beach, South Carolina, October 1987.
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a J. L. Hardee and G. E. Liepins " Expert Systems for Personnel Assignment," Proceedings of the Twenty-Second Annual Meeting of The Institute for Management Sciences, Southeastern Chapter, Mynle Beach, South Carolina, October 1986.
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l PROFESSIONAL EXPERIENCE SU5131ARY K. St. Johnson N!ichelle Johnson is a research engineer for JBF Associates. Inc. She has 17 years of experience in system reliability engineering. safety analysis. a nd risk assessment. A graduate of the University of Tennessee.
Nia. Johnson holds B.S. and N1.E. degree >. in nuclear engineering and is a registered Professional Engineer in the state of Tennessee.
Since becoming a consultant to the Nuclear Operations Analysis Center (NOAC) 14 years ago, Ms. Johnson has worked with the NOAC staff on several projects for the U.S. Nuclear Regulatory Commission (NRC),
including the development and implementation of the Sequence Coding and Search System (SCSS), a data base for nuclear power plant event data. Her responsibilities on SCSS have involved the review and analysis ofevents and the encoding of data from the events, interaction with NRC staff to define and meet operational data needs, and conducting special studies and reviews of plant operating histories to support NRC Diagnostic Evaluations. Ms. Johnson has also supponed Unresolved Safety issue A-17, NOAC's project on adverse System Interactions and evaluated event data and risk assessment methodologies. Ms. Johnson v.as involved in a safety review of the CANDU 300 conceptual design. She reviewed operating experience data for pressurized heavy water reactors and selected events of interest (i.e., common-cause events, adverse system interaction events, and accident-initiating events).
Earlier, while on the TVA stafT. Ms. Johnson was a member of the utility's accident analysis group, assessing accident sequences for the Browns Ferry and Sequoyah plants. Other experience at TVA involved the review of testing procedures as a part of a preoperational testing group and the analysis of subcompartment pressures for several TVA plants.
Ms. Johnson's experiences in the area of system reliability and risk assessment include an assessment of the safety hazara to personnel working in the weapons production facilities at the Department of Energy's (DOE) Y-12 Plant in Oak Ridge, TN (an assessment that involved evaluating administrative, transportation, and technical procedures associated with handling hazardous and radioactive materials). Recently she has been involved in efforts to support licensing of the Paducah and Ponsmouth Gaseous Diffusion Plants (GDPs) by the NRC. Ms. Johnson managed and performed several qualitative and quantitative analyses of the feed and withdrawal operations at both GDPs. She was also involved in developing tech iical safety requirements for the feed operations at both plants. She also helped prepare a system evaluation for the Clinch River Breeder Reactor Plant PRA Study in addition to assisting in the development of an equipment failure data base for use with statistical analysis routines. Other projects in which she has participated include the development of a computer model for common-cause failure analysis, a risk evaluation study of waste sites
, at the Savannah River Site (SRS), and development of operational safety requirements for a solid waste l management facility and a liquid waste vitrification facility at SRS.
l Ms. Johnson has also performed several hazard and operability (HAZOP) reviews of hydrocarbon shipping
! and storage systems and a liquified natural gas cargo ship. She has experience with numerous PRA techniques including HAZOP, FMEA, event tree analysis, CCF analysis, and FTA and has experience using the (RRAS computer program.
l
l Barbara M. King
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' ' email: b9a & ornl. gov EDUCATION Auburn University Auburn. AL l
= Master of Computer Science and EngineeringM l
- Master design project titled " Compare and Contras't tile i Capabilities and Limitations of HTML. Java and VRML" University of Tennessee Knoxville. TN
. Bachelor of Science. Computer Science. G l
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EXPERIENCE ,
07/91 - Present Lockheed Martin Energy Systems Oak Ridge. TN l Computer.4nalyst
. Experience in documentation and quality assurance l Web client-server design and construction l =
!
- HTML page layout ,
= Java /Javascript l 12/89- 07/91 Ridgeview Psychiatric Ilospital & Center Oak Ridge, TN Data Processing Clerk Data entry ofclient char;;es and payments
. Testing new programs LANGUAGES C, Cm Ada. LISP. Java ADDITIONAL INFORMATION l
Received recognition / Operations and Support award for documentation and quality assurance in 1994 i
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- . j i
' e-mail: j9zttornt. gov John Martellaro 423-576-o840 (work) .
- i Profile ,
! I am a physiast by trairung with a considerable amount of expenence m computer technology, research, techrucal wnting, oral presentations and protect management. I am l
currently speaalizing m mformation technologies, and I have a balanced mix of a strong technical background and good people skills.
Skills Eroblem solvinc: Performed applied and theoretical research in electromagnetism at '
several research laboratories. Strong mathematical background from Ph.D. work.
Comouters and lancuacee Internet and Macmtosh expert. Six years expenence m C and C++. Very expenenced in the followmg areas: simulations, modeling, man-machine interfaces, Unix (OSF/1 and Irix), Windows, TCP/IP, RISC technology, database theory and design , DAL, ODBC, SQL CUI tools, HTML, and HTTP. Expenence with PERL and WinNT. Prevmus expenence in Fortran, Simscript and Pascal, CASE (IEF), and Maantosh development: XVT , Symantec, & Code Warnor. Certified Unix system administrator.
Physics: Strong m electromagnetism and optics including propagation of EM waves in matenals. Exceptional background in Astronomy (relativity, optics), sensors, and orbital mechanics.
Procram Manacement: Twenty years expenence in saentific team management, technical wnting and stand-up bnefings with the Govemment and pnvate industry.
Education BS. Astrophysics, Indiana University,M M.S. Physics,(Quantum Mechanics) Uhiversity of West Flonda @
Worked on Ph.D. in Physics, New Mexico State Universityg '
(General Relativity & Electromagnetism)
Experience
- 1. Research Staff Member (Jul 91 - present) Data Systems Research & Development, Lockheed Martm Energy Systems, The Oak Ridge Reservation. Program manager for two years doing Operations Research in Al tools and man-machine interfaces for Army Command
& Control systems. Work on the Future Theater Level Model validation received several commendations. Two years 4GL programnung in the EMPRESS database system. Developed PC SQL client front ends connected via DAL and ODBC to Infomtix and Orade 7 on DEC Alphas. Designed and installed a database system for the Cw.munity Relations Division.
Installed filTP servers for our division and assisted in the restructure of the division network architecture. Developed the Maantosh part of our Electroruc Information Network Program in WAIS technology. Developed a dient/ server prototype for a company-wide payroll system. Currently working on: 1) Data warehouse development for our three site's Waste Tracking Systems and 2) An Electronic Data Interchange Server for the CALS project.
Division liason to Apple Computer. Named Division Senior Techrucal Advisor on PC Technologies. Instrumentalin the development of Intemet Technologies company-wide as a l
member of the Intemet Technologies Coordinating Council.
- 2. Sr. Research Scientist (Feb 87 - Jun 91), Martin Manetta Astronautics, Denver, Colorado.
Worked in the Advanced Research Laboratory doing advanced R & D in electromagnetic l wave interaction with matenals. Made extensive use of large EM models. Managed three I
$200K technology development subcontracts. For work in developmg, analyzmg and testing a new matenal, received an employee commendation award (December 89) and promoted in March 1991.
- 3. Staff Enemeer (Nov 85 - Feb 87), Martin Manetta Astronautics, Denver, Colorado.,
Worked on several space research defense programs perforTning applied R&D managing
)
-* onginal research in ablatives and laser discnnunation of RV decoys. l r '
l 4. Operations Re ,carch Analyst (1982 - 1985), U.S. Army, Trairung and Dddnne Command, White Sands, New Mexico,(CS-12). Team member and arclutect of the CASTFOREM expert system / combat model. Wrote the code (Simscnpt) for all simulation physics and damage assessment. Successfully integrated the functional charactenstic of laser weapons -
into the model utilizing the White Sands Atmosphenc Science Lab laser /atmosphenc models. Gained extensive expenence in large model development, j 1
Military Experience USAF Officer,(1%9-73). Worked for the Aerospace Defense Command at Spacetrack radars ]
in Flonda and Diyarbakir, Turkey. Gained expenence in radar systems, orbital analysis, and radar signature analysis. Reached grade of Captain and supervised 4 officers and 12 enlisted in final year. Computenzed the Altemate Space Defense Center Space Object identification l database resulting in a letter of commendation from the site commander.
1 Honors & Awards ]
Honor graduate of USAF Space Object identification School, Keesler AFB, MS,1%9 Commendation Letter,20th Surveillance Squadron, Eglin AFB,1973 l Sigma Pi Sigma (National Physics Honorarv), University of West Florida,1973 1 Sigma Xi (National Research Honorary), Uruversity of West Florida,1974 Papers presented in Dallas at the AIAA Student Paper competition won 2nd & 1st place awards-respectively in 1978 and 1979 Charles Mansur Award, AIA A. White Sands New Mexico Chapter,1979 ;
- Exceptional Performance Award, U.S. Army, TRADOC, White Sands, NM,1983 L
Sustained Supenor Performance Award, U.S. Army, TRADOC, White Sands, NM,1985 Employee Commendation, Advanced Researth Laboratory, Martin Marietta, Denver, CO,1989 l Technology Development Award, Data Sy' stems R&D, Martm Manetta Energy Systems, Oak l Ridge, TN,1992
. Technical Innovation Award, Data Systems R&D, Martin Manetta Energy Systems, Oak Ridge, i TN,1994 %- l i
References Len Sugerman, Col. USAF, Ret. , Las Cruces, NM,505.522 7842 !
Jim Walker, Program Manager, Martin Manetta, Denver, CO,303.971.8494 i
Michael Weasner, Program Manager, TRW Corp, El Segundo, CA,310.814.6752 Previous part time work in Graduate Schoch .
Programmer ohvsicist. (1980-1981) for Applied Science Associates, El Paso Texas. Worked l on a contract with Directorate of Combat Developments, Ft Bliss, to upgrade the Patriot Missile Simulator for psychological researth (operator workload). Gained experience in l' combat simulation for air defense, human factors in weapon system design, and large model i
l management . Physicist. (1979-1980) Physical Science Laboratory, New Mexico State Univ, Prinnnal Investientor on a contract with Office of Missile Electronic Warfare, White Sands Missile Range to explore the technology of a new infrared jammmg technique.
Supervised a team of five including two Ph.Ds. Aerosnace Fneinser. (Summers 1977,1978)
{
N ASA,' Johnson Space Center, Houston, TX. Summer intem, (GS-9, one of only 50 selected nationwide), assigned to research the capabilities of all Space Shuttle simulators for i emergency flight support (1977). Designed and wrote contingency Shuttic rescheduling
. algonthms (1978). Physicist. (1973-1974) Eglin AFB Armament and Development Lab, j Florida (GS-7). Researched the infrared and visible properties of jet engine plumes using
' molecular spectroscopy and line reversal. Designed an array infrared radiometer.
Security Clearances DOD Secret Clearance. Marun Marietta. Denver (5 Dec 85)
EBI/ SCI -213-2178 (22 Dec 87), Cor.nter Intel Polygraph (14 Aug 89), Martin Marietta.
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ELEMENTS OF COST SCHEDULE Worksheet FOR WAS FIELD WORK PROPOSAL AND
' WORK FOR OTHERS ESTIMATES (Dollers in Thousands) 41 W913 4A 1 Division ETO 16 i
Combined Tasks '
I Resource Program Activity No.
Probability 1 New Budget Proposal X Revised Budget Proposal Date Prepared August 19.1996 CHECK: **
Principal investigator i Pr!p;ted By 4 W. P. Poore. Ill W. P. Poore. D. T. Cannon i Control No. (FWP/189) Title ,
A9134 Seouence Coding and Search System j Fiscal Year Estimates FY 1996 FY 1996 FY 1997 FY 1998 FY 1999 ,
item '
- PY s PY $ PY $
Summary by Major Elements PY 8
-4 5 40 0 0 Materials - Non Exempt J 0 16 0 0 J M Metenals Exempt 0 0.0 0 0.0 0 0.0 0 00 3 j J A Subcontract Non Exempt 0.0 '
1.1 16 243 1.2 42 0.2 0 4 4 T Subcontract Exempt 205 3..
t 2 6 1 0 J L Travel .
202 1.1 329 1.6 306 1.2 43 0.2 0 0.0 6 TOTAL . Meternels 300 2.3 227 1.5 501 3.5 124 0.9 0 0.0 J C Intra. Division Cost Centers 0 0.0 1'8 1.5 373 3.2 101 0.8 23 0.2 J N Inter. Division Cost Centers 0.0 0 0.0 0 0.0 0 0.0 0 J T Leased Employee 0 0.0 478 - 3.8 580 4.7 602 4.3 147 1.1 '
10 R TOTAL Cost Centere =
0 0 0.0 0 0.0 0 0.0 0.0_
- y Health & Safety Services 0 0.0 0 0.0 0 0.0 0 0.0 .j R 1 i & C Services 0 0.0 0 0.0 0 0.0 0 0.0 y N P & E Servicae 0 0.0 0 0.0 0 0.0 0 0.0 3 T Qual tv Services 0 0 0 0 Utilitsee . Non Exempt 3 R Utilities - Exempt 0 0 0 0 4
3 A- 0 0.0 0 0.0 0 0.0 0 0.0 y Waste Monocement Services 9 0 0.0 0 0.0 0 0.0 0 0.0 3 0 Other intra OU Services 0.0 0 0.0 TOTAL Intre OU Sup. Serv. 9 0.0 0 0.0 0 0.0 0 19 U 0 0.0 y
Analytical Services Organization ' O 0.0 0 0.0 0 0.0 0
2,0, 0 0.0 q
19 20 0.0 5 0.0 0 0.0 i 21 C Computer & Programmino Services 0 0.0 0 0.0 0 0.0 0 0.0 Central Engineerino Services
^
R E IR&A Services 0 0.0 3 0.0 1 0.0 0 0.0 l 23 N 0.0 0 0.0 6 0.0 2 0.0 1 M
T Procurement 0 0.0 0 0.0 0 0.0 0 00 g R Telecommunicatione 32 0.0 32 0.0 7 0.0 0 0.0 g A Other Central Support Services 0.0 58 0.0 42 0.0 9 0.0 0 0.0 27 L TOTAL Centrol Sup. Serv. 19 s
0 0.0 0 0.0 0 0.0 0 0.0 1
28 K 25 0.0 0 0.0 0.0 0 0.0 0 Y Y-12 0 0.0 0 0.0 0 0.0 0 0.0 Y Other Operatine Unets 0 0.0 0 0.0 0 0.0 0 0.0 Y TOTAL Other OU Sup. Serv. 0 0.0 0 0 0 _, 0 indirect Charges '
32 m) 316 314 0 33 O Overhead 235
- O O 4g 0
[ ,/ Overhead - Other Setes 35 H TOTAL Overhead Coste i 236 316 314 0
6.3 1263 6.6 266 1.3 0 0.0 36 GRAND TOTAL ~ 943 4.9 1283 OFA Program 40 Added Factor 41 E Revised GRAND TOTAL - OFA Only 984 4.9 1283 6.3 1263 5.5 266 1.3 0 0.0 38 0 0 3
Memo Only BA 1216 978 1140 l
39 Memo Only . Capital Eauspment l 3 Memo Only End. Uncosted Bat. 694 389 266 0 3 Memo Only CRADAs 42 (R:vi:ed 1/961 f
4 l
ORNL TECHNICAL / FINANCIAL INFORMATION SYSTEM (TFIS)
SUPPLEMENTAL INFORMATION FORM FOR FY 1996 BUDGET REVIEW COMPLETE THE FOLLOWING FOR ALL PROJECTS (DOE AND WFO):
B&R NO.: 4 I Wo I t 4 A i FWP No.. \9134 DATE. R ?! '96 MANAGER BADGE. 2171' START DATE. EST. COMP DATE.
ASSOCIATE DIRECTOR: I o %ecier. 06 TCODE. W413S TITLE (Short) Secuence Codine and Search wrem isCS9 DOE-ORO MANAGER: S R Martm DOE-HO MANAGER.
ABSTRACT The Nuclear Operations Analysis Center tNOAC)is assistmg tre NRC Office for Analysis and Evaluation of Operational Data (AEOD) m the appheation and operation of the Sequense Codtng and Search System (SCSS). This program involves a system where engmeers familiar with the opera: ion of commercial nuclear power plants evaluate plant problems reported in Licensee Event Reports (LERs) from a safety perspective and then document the evaluations in the SCSS database in a stnictured format.
This format permits detailed coding of component sy stern. and urut etTects as well as personnel errors. It directly supports NRC staff needs pertaining to nuclear plant sa:ety and performance issues and other NRC programs requiring timely access to operational esent data.
TYPE OF ACTIVITY: (INDICATE %-MUST ADD TO 100%)
- 1. BASIC RESEARCH 3. EXPLORATORY DEv 5. ENGINEERING DEV 100 2. APPLIED RESEARCH 4 ADVANCED DEv 6. NON R&D CROSSCUTS: (INDICATE %-MUST ADO TO AT LEAST 100%)
- 1. ADVANCED MANUFACTURING 6 SUPERCOMPUTERS 10. ENVIRONMENTAL
- 2. ADVANCED MATERIALS 7. SUPERCONDUCTMTY 11. EDUCATION AL
- 3. BIOTECHNOLOGY 8. OCCUPATION SAFETY ACTMTIES
- 4. MATH & SCIENCE ED 9. OCCUPATION HEALTH 12. GLOBAL CHANGE
- 5. SEMICONDUCTORS 100 13. OTHER INITIATIVES: (INDICATE %-NEED NOT @D TO 100%)
- 1. ADVANCED NEUTRON 4 ADVANCED MATERLALS 7. STRUCTURAL SOURCE 5. COMPUTATIONAL BIOLOGY
- 2. LIFE SCIENCES SCIENCE 8. BIOTECHNOLOGY COMPLEX 6. TRANSPORTATION 9. OTHER
- 3. MATERIAL SCIENCE & TECHNOLOGIES ENGINEER COMPLEX COMPLETE THE FOLLOWING FOR WFO PROJECTS ONLY:
I DOE NO.: I886-8913-4 A DOE BR: 40 10 01 10 PROJECT MANAGER W P Poore l
l
! PROGRAM: 41 FUND CODE: BILLING WO. PI: D T. Cannon AGENCY CODE: REA SPONSOR: NRC/AEOD BEGINNING UNCOSTED BALANCE S666 DIVISION. ETD (14 Di SECTION: PROB: I
4
- =n::= : >
OATE PROPOSAL SENT 'q NP. ; Form 189 (Part 1) U.S. NUCLEAR REGULATORY COMMISSION (10 93) .*"* . 08 21 96 l NRCMD 11.7
( DOE LABORATORY PROJECT AND stw ry % j
.r.. ' COST PROPOSAL FOR NRC WORK x ' aevision : suusts i !
PROJECT TITLE JOB COCE Seauence Codine and Search Ssstem A9134 NRC OFFICE NRC B&R NUMBER Analysis and Evaluation of Operanonal Data 582-15-11-60 35 DCE CONTRACICR NRC BOC CCCE Lockheed Martin Enerc3 Research Corp. 253D SITE CONTRACTOR ACCOUNT NUMBER Oak Ridge National Laboratory 4I W913 4A 1 Oak Ridee. T.nnessee 37831 COGNIZANT PERSONNEL ORGANIZ.ATION TELEPHONE NO. DOE B&R NUMBER l NRC PROJECT MANAGER 40 10 01 10 l D. E. Yeilding AEOL, (301)415-6355 j OTHER NRC TECHNICAL STAFF PERIOD OF PERFORMANCE DOE PROJECT MANAGER PROJECT START DATE 1 S. R. Martin DOE-ORO (423)S76-4522 07/01/80 LABORATORY PROGRAM DIRECTOR PROJECT END DATE I C. E. Pugn ORNL-CMO (423)574-0422 12/31/97
);
LABORATORY PROJECT MANAGER ,, .
W. P. Poore ORNL-ETD (423) 574-0325 , p 3., ,
PRINCIPAL INVESTIGATOR (S)
~
LFT D. T. Cannon K25 -DSRD (423)574-8940 -
KEY PERSONNEL
. M ,'. '". '
W. E. Kohn ORNL-ETD (423)574-0379 1- 5~" JM$h A. J. Martellaro K25-DSRD (423)576-6840 I O DT' K. M. Johnson JBF (423)671-5820 J. A. Farquharson JBF (423)671 5807 . % E ' .O
,J Fa #
L. E. Palko J. J. Rooney JBF mF (423) 67l-5839 (4W 671-5 814 j
- f,QWfi STAFF YEARS OF EFFORT FY 1995 FY 1996 FY 1997 FY 1998 FY DIRECT SCIENTIFIC / TECHNICAL 4.9 6.3 5.5 1.3 OTHER DIRECT (Support Servces)
TOTAL DIRECT STAFF YEARS 49 63 5.5 1.3 00 COST PROPOSAL (Roma in Nearesi thousann s> ,
F G DIRECT LABOR (Scientific /Techncal) , 580 607 I OVERHEAD (included in Direct Labor) I
'~~
MATERIALS / SERVICES @ 63 98 O '
FOREIGN i ,
DOMESTIC @ ^
2 6 '
SUBCONTRACT (S) i 322 243 $
OTHER DIRECT _
GENERAUADMINISTRATIVE EXPENSES 235 316 314 67 TOTAL ESTIMATED LABORATORY 943 1.283 1,263 266 0 PROJECT COST DOE ADDED FACTOR 41 0 0 0 TOTAL DOE PROJECT COST 984 1.283 1.263 266 0 CARRYOVER FROM PRIOR FY 462 694 389 266 0 CARRYOVER TO NEXT FY 694 389 266 0 1 TOTAL FUNDING REQUIRED $ 1.216 $978 51.140 50 50 !
NFtG Form 16s16-951 1
a 6-NR.: Form 189 (Part 2) U.S. NUCLEAR REGULATORY COMMISSION JOB CCCE j (10 93) A9134 l NRCMD 11.7 DOE LABORATORY PROJECT AND gg7g COST PROPOSAL FOR NRC WORK 08/21 96 FOR PROJECTS EXCLUDING TASK ORDERS AND TASK ORDER AGREEMENTS PROJECT TITLE. Sequence Coding and Search 53 stem
' DOE PROPOSING ORGANIZATION Lockheed Martin Energy Research Corp.
Oak Ridge National Laboratory ESTIMATED COST BY TASK ($K)"
TASK 1 TASK 2 TASK 3 TASK 4 TASKS 2,105 400 61 195 154 TASK 6 TASK 7 TASK 8 TASK 9 TASK 10 22 763 5 9 7 TASK 11 TASK 12 TASK 13 TASK 14 TASK 15 75 TASK 16 TASK 17 TASK 18 TASK 19 TASK 20 TASK 21 TASK 22 TASK 23 TASK 24 TASK 25 PROJECT DESCRIPTION A NARRAllVE DESCRIPTION IS PROVIDED ON EACH OF THE FOLLO'MNG TOPICS IN THe. ORDER LISTED.
1 OBJECTIVES OF PROPOSED WORK 8 REPORTING REQUIREMENTS AND SCHEDULE
- 2.
SUMMARY
OF PRIOR EFFORTS 9 SUBCONTRACTOR / CONSULTANT AND MAJOR PROCUREMENT INFORMATION*
- 3. WORK TO BE PERFORMED AND EXPECTED RESULTS 10 SPECIAL FACILITIES, IF REQUIRED ;
! 4 PROPOSED PERSONNEL-INCLUDE RESUMES . 11. CONFLICT.0F. INTEREST INFORMATION
- 5. MEETINGS / TRAVEL 12. CLASSIFICATION OR SENSITIVITY. IF APPLICABLE (e g , safeguards, propnetary, other) 6 NRC FURNISHED MATERIALS 13 ADDENDUM (A) INTERPRETATIONS OF STATEMENT l
OF WORK. (B) COST INFORMATION AND (C) ,
SCHEDULE INFORMATION
- 7. RELATIONSHIP TO OTHER PROJECTS 14 SPENDING PLAN l
i
- PROJECTS WITH COST. TYPE SUBCONTRACTS CANNOT BE CLOSED OUT UNTIL REQUIRED DCAA AUDITS HAVE BEEN CONDUCTED.
" Cost estrnates pertain to the October 1.1995, througn December 31.1997, penod OATE SIGNATURE-APPROVA UTHORITY C. E. Puch. Director. NRC Procrams NRC Form 189 (6-95)
l r
l NRC Form 189 (Contmued) U.S. NUCLEAR REGULAT ORY COMMISSION JOB CODE !
,\9134 (10 93)
NRCM011.7 DOE LABORATORY PROJECT AND DATE COST PROPOSAL FOR NRC WORK 08,21.96 PROJECT TITLE Sequence Coding and Search System j
- 1. OBJECTIVES OF PROPOSED WORK: j 1
The Nuclear Operations Analysis Center iNOAC)is assisting the Nuclear Regulators CommissioTs (NRC's) Omce for Analysis and Esaluation of Operational Data ( AEOD) in the maintenance and operation of the Sequence Coding and Search System iSCSS).
This program involves a system for reducmg the desenptne test contamed m Licensee Esent Reports (LERs) to coded sequences .
that are both computer readable and computer searchable. The system prosides a structured format for detailed coding of component. system, and umt etTects, as well as personnel errors. The SCSS provides a more emcient and sophisticated LER data retrieval tool than any sy stem currently in existence.
Additional Details SCSS Oneration: Some dictmetive features of the SCSS :tre: ia) advanced and emcient search techniques. Ib) information from the LER's supplemental data sheets for pre-1984 LERs and from the narratne description for LERs occurring on or atter January 1.
1984. (c) codes that categorize the components m both tine t specifici and coarse t generici detail. (d) components are identified by I i
system. (e) personnel actions described in detail. (f) the loss of one or more tratns and/or systems are identified. (g) events involving one or more systems are identified. (h) precursor and successor occurrences in a sequence are identified. (i) multiple initiators of an esent (if they exist) are identified. (j) information regarding unit etTects. radiological releases, and exposures is accessible, j (k) detailed information on reactor protection system (RPS) actuations (scrams) and engineered safety feature (ESF) actuations is I available and (l) data on the " root or " basic" cause of the event are provided. The database management sy stem employed provides capabilities for performtng a number of statistical and analytical functions on-line. The database is available for interactive access to some 80 users located at NRC Headquarters and regional offices as well as selected national laboratories and other contractors.
SCSS Utilization: NOAC provides NRC, NRC contractors, and other gournment agencies (upon AEOD approval) a central point l for assistance in defming and solving their nuclear safety questions and assistance with their information needs related to operational experience data. Prior to FY 1994, etTort on this task was supported under Job Code A9135-Sequence Coding and Scarch System L'tilization.
Effective December 31, 1986, DOE termmated funding of the RECON system or, which the NOAC master file resided.
NRC-AEOD initiated etTorts during FY 1987 with vendors to make the NOAC file available commercially. Negotiations were carried out through the National Technical Information Services. but no agreements were finalized. Consequently, LER data prior to 1980 is accessible only via batch searches conducted at NOAC.
The SCSS file of LERs is NRC's omcial repository for LERs since NRC's National Institute of Health (NIH) file was discontinued at the end of CY 1981. AEOD continues to utilize the database extensively. From FY 1987 through May 1996, NOAC stafThas provided assistance to AEOD through either (a) conducting searches directly or (b) providing search strategies for some 544 requests. SCSS now contains over 42.000 LERs with event dates from 1980 through March 1996. In addition to NOAC, a total of approximately 80 users currently have access to SCSS.
In addition to supporting AEOD. NOAC ir,teracts with the stafTof the Office of Nuclear Reactor Regulation. the Office of Nuclear Regulatory Research. the various NRC regional offices. and selected national laboratories conductmg NRC-sponsored work. From FY 1987 through May 1996. NOAC has responded to approximately 932 requests from these NRC offices, contractors, and industry l for LER data using SCSS. NOAC has developed a user-friendly, menu-driven interface to facilitate usage of SCSS by NRC staff.
l A group ofinitial users began testing the interface in August 1991.
l Also. NRC has supplied data to support approximately 86 requests from the industry on a cost-recovery basis since 1987.
I SCSS Develonment: The sequence coding of LERs on a routine basis began with the 1981 events following a pilot program demonstrating the SCSS concept m late 1980. Since that time, additional modifications and retinements have been made in the coding procedures as well as the software of the database management systems which have been used to manace the SCSS LE w r~ m me ,, ,
hrs, Form 189 (Contmued) U.S. NUCLEAR REGULATORY COMMISSION l.08 CCPE l (10 93) l A9134 i NRCMDit7 DOE LABORATORY PROJECT AND DATC~
4 l COST PROPOSAL FOR NRC WORK og ,; ne ]
i i
PROJECT 'TLE Sequence Cedmg and Search Sy stem h'
=
Jata. In late 1032 and early 1083. 3!aw respon3e umes were enccuntereJ when searching ins SCSS corrputer file using System IC on the DEC-10 computer The JOSHl'A sy stem. which is a ba3lc data handhng system that operates on IBN1-compatible computers and requires f ORTRANfrogrammmg. was pursued on a :na! basiv The tnal program was successfully completed by late FY 1%3 and the SCSS database was totally conserted to JOS}ll'A m Starcn 1984 System search and data retrieval capabilities hase continued to be enhanced and augmented with new software features and sub3equently documented in the SCSS User's Guide revisions issued m December 1985 and September 1989 During FY 1992. a report was issued which documented feedback trom <
a group of test users of a PC based SCSS Front End Processor. This software serses as an intuitise. user triendly interface between the SCSS user and the mainframe-based SCSS database. Esolsm; hardware and software capabihties oser the last few years prompted conducting a teasibility study to consider operatmg the SCSS database on a different computer platform. The feasibihts study completed in FY 1992. reached the conclusion that the SCSS database could be operated on a smaller and more economical computer systern than the IGN1 companble mainframe and that new database management software would offer more intuitise. user-friendly features than presently asailable with JOS!!UA Suoxquent!> in FY !W3 a program plan was created to guide the transition to a workstanon-based system which was implemented in FY 1944 as initial etTorts to errect the transinon were made A cost sasing deselopment erfort to estract abstracts trom LER5 receised electromcally trom the NRC's Nuclear Documents Sy stem
( NUDOCS) was completed durmg FY 1992, in September 1093. the SCSS database was mosed from the IGN13090 to a newer.
more pow erful IBN1-companble mamframe computer sy stem Through FY 1994, development acnuties were supponed under Job Code A9451-Sequence Coding and Search S: stem Development. Beginnmg in FY 1995, development actiuties were carned out under Job Code A9134-Sequence Coding and Search System.
Tork for FY 1996 j l
The work is organized into the following tasks for FY 1996.
Task 1-Routme Codine and Addition ofI ERs to sCSS File. Starting with LERs with 1980 event dates, all codable LERs hase oeen '
coded, prc<essed, and added to the SCSS database. These acuuties will contmue routinely for new LERs as they are received. De steady-state processing time is to be maintained at two weeks durtng FY 1996.
Task 2 Ouality Assurance Procram for Codine and Processme LERs. A quality assurance (QA) program for assuring consistency in the coding and processing of LERs has been developed as documented in Sequence Codmg andSearch System Qualin Assurance Program. ORNL/NOAC-225. Resision 3 (September 1991). The QA program is executed in a manner consistent with procedures desenbed therein. (The QA Manual will be updated and mamtatned to reflect modifications to the QA program implemented during FY 1995 under Task 3.)
Task 3-SCSS Database Documentation. De SCSS Coder 's Manual. Programmer 's Manual User 's Guide. QA Program Manual.
Front-End Processor Manual. and SCSS On-Line Help Files will be updated and maintained as required to reflect rule changes.
code definition changes, etc.. which may affect the consistency and accuracy of the sequence coding. Such . dditions and chances will be issued as amendments to be incorporated in the respective manuals.
Task 4-Resnondine to inauiries and Utilization of Data. Response to informanonal needs of NRC will utilize SCSS and other l
resources at NOAC. Response to nonexempt requests will be handled upon approval by AEOD or through a full cost-recc'.ery program. Requests for LER abstracts and keywords will also be handled under this task.
l Task 5-Technical Assistance. AEOD may need techmcal assistance on speci6c topics requiring high-pnonts, quick-turnaround tasks. These tasks will be of a short-term nature.
Task 6 NRC StatTTrainine. NOAC shall develop presentauons on capabihties of SCSS for various NRC offices to illustrate how SCSS could be used to support NRC statT.
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NRC Form 189 (Contmued) U.F. NUCLEAR REGUJTORY COMN. 3SION JOB CODE (10 93) A9134 l NRCMD 11.7 DOE LABORATORY PROJECT AND DATE COST PROPOSAL FOR NRC WORK 080196 i PROJECT TITLE Sequence Coding and Search System I
l Task '-sCSS Workstation Consersion A scoping study completed m FY 1992 concluded that it is feasible to operate the SCSS - l database on a smaller, more economical platform tworkstations with more intuitise, user-friendly software than the current mainframe-based system. At AEOD's request. minimal etTorts were espended on this task during FY 1993. For FY 1094. work to begin implementanon of this transition was staned A detailed SCSS daubase descr.ption will be prepared to document the necessary and desired features required for the replacement software. Thir will be followed by recommendations of specit'ic-replacement hardware and software to purchase. The deselopment of the SCSS database application on the replacement software started during FY 1994 and will be completed in FY 1997. FY 1997 etTorts will also include a period of testmg and concurrent operanon of the current and replacement sy stems to ensure satisfactory performance and operation.
Task 8-Mainframe. Based Front-End Processor l'ndates NOAC shall continue the development and further refinement of the front-end processor (FEP) for SCSS. which is to provide a user-friendly interface to facilitate searching SCSS.
Task 9-ORNLINEL i ER Database Consolidation This task is to esamine seseral Idaho National Engineering Laboratory (INEL)
LER database specifications and evaluate the abilits of SCSS in its present and future forms to capture and retain this information so that multiple, labor-intensise LER reviews and data processmg activities can be reduced. It also includes the preparation of a project plan depicting the required tasks. schedule, and milestones to implement the consolidation of LER codmg into the new SCSS database to be maintained on a workstation.
Task 10-SCSS Common Cause Failure Analvsis. This task is to develop and implement SCSS search strategies to identify potential common cause failures and independent failures reported in LER data for studies of selected components and systems by the NRC and/or its contractors.
Task !!-Technical Assistance to Suncort an Independent Safety Assessment. This tasx is for the performance of reliability ard risk-based analysis of selected systems and testing support evaluatio.i as part of an Independent Safety Assessment (ISA) at the Maine Yankee nuclear power plant.
- 2. SUMM ARY OF PRIOR EFFORTS:
SCSS Operations The feasibility of the Sequence Coding and Search System was demonstrated in FY 1981. During FY 1982, reftnements were made in both the coding and the programmmg. The coding was extended by including additional data fields. The computer software was improved to include additional internal checks for quality control. Since this time, LERs have been routinely coded and added to the database.
A draft version of the Coder's Afanual was issued in March 1983 and subsequently reissued as Revision 0 in March 1984 with several amendments to Revision 0 issued during FY 1984. Revision I to the Coder's Afanualwas issued in November 1984, with Amendments I,2,3,4, and 5 to P,evision I being added in April, July, and October 1985, and January and August of 1986.
respectively. Amendments 6 and 7 were issued in March and September 1987, respectively. No amendments were issued in FY 1988 in view of reduced funding. Amendment 8, which discussed the assignment of cause and corrective action data, was issued
! in September 1989. Amendment 9 was completed in September 1990. Revision A of Volume 3 of the Coder's Afanualwas issued l in September 1991. The Coder's Afanualdetails the coding process and includes rules for use of the codes.
Formal documentation on SCSS was issued in April 1985 with the publication of the four volumes of NUREG'CR-3905 (ORNLNSIC-223), Sequence Codmg andSearch Systemfor Licensee Event Reports. The four volumes included one each for the User 's Guide and Code Listings and two for the Coder 's Afanual.
The SCSS database was developed on the DEC-10 computer system utilizing System 1022 as the database management system.
The database evolved from three data sets to seven on 1022 to meet AEOD requirements. The User's Guide was issued in a,-
NRC Fem 189 (6-9s) _ _
1 i
l fl NRC Form 189 (Continued) U.S. NUCLEAR REGULATORY CO 1 MISSION JOB CCCE l l
6093) .19134 l NRCMD 11.7 DOE LABORATORY PROJECT AND DATE COST PROPOSAL FOR NRC WORK 08/2096 PROJECT TITLE. Sequence Coding and Search System n ,,
April 1982 and rnised in July 1983 in late 1982 and early 1983, problems were encountered on the DEC-10 computer in terms of unacceptable response time. Following seseral months of etTorts to unJerstand the problem on the DEC-10 and study other l computer database management systems, a trial program aas conducted by loadtng the SCSS database on the JOSHUA system !
which. as of FY 1989. operated on the IBM-3033 computer. < A more powerful IBM 3090 computer replaced the IBM 3033 in FY 1989a The trial program was successfully completed in late FY 1983. and the SCSS database was totally con erted to the JOSHUA system in March 1984. A drad of the User x Gaade for the JOSHUA sy stem for SCSS was issued in January 1984, revned in May 1984, and a final version issued in August 1984. Sy stem search and data retrieval capabilities have continued to be enhanced and augmented with the implementation of rcew software features since FY 1984. Revised pages to reflect changes in codes used following the retrofit of the database in December 1984 were issued in February 1985, and amendments describing new software capabilities were published in August and December 1985.
During 1986, two major changes to the oserall process of adding LER data to SCSS were implemented. First, in March 1986, the coding process was modified to begin coding LERs directly on line interactnely sersus submitting paper forms for data entry sia keypunch operanons. The QA review and scan operations are performed on line as well. Computer QA checks are execu:ed at each of the three processing stages, thus prouding tmmediate feedback at each stage of the overall process. Secondly, starting also in March 1986, the majority of LER abstracts were being entered via an optical character reader (OCR) for subsequent matching with the SCSS matrix.
In January 1986, an IBM disk dedicated to supporting SCSS computer activities was installed to accommodate the 20,000- LER records on SCSS at that time and other supplemental files.
Starting in FY 1987 with the 1987 LERs. new codes were implemented for ESF actuations, RPS actuations, and event causes to provide more detailed infonnation. The new ESF codes designated the cause for the ESF it;lf, the ESF system (s) actuated, the generic ESF type (isolation, injection, ventilation. etc.i. the activity being performed when the ESF occurred, and the parameterts) that actuated the ESF (flow, pressure, temperature, radiation, etc.).
The new RPS actuation codes identified the cause of the RPS actuation, the activity being performed when the RPS actuation occurred, and the parameterts) that actuated the RPS actuation shutdown (flow, pressure, temperature, radiation, etc.). The event cause codes, which were assigned in addition to the cause codes assigned for each step, consist of Watchlist codes that specify the overall cause of the esent itself.
For FY 1988, principal efTorts focused on the processing of LERs. The overall QA program was reduced in scope, and the vanous manuals were not updated in order to be consistent with available funding levels.
For FY 1989, the routine processing schedule was reduced from four weeks to two weeks in April 1989 to support the assignment of cause and corrective action codes to LERs (Job Code F0052). The routine assignment of programmatic cause and corrective action data based on engineering review was incorporated into the SCSS coding process starting with the 1989 LERs. Search l strategies developed to map the cause code definitions were executed following the coding of an LER to check the initial assignment of cause codes.
During FY 1989, NOAC began investigating the possibility of using abstracts of LERs supplied from NRC's Nuclear Do' cuments System (NUDOCS). Initial efibrts invoked reading the abstracts som tapes received from NRC's contractor for NUDOCS.
Difficulties were experienced in the accuracy and completeness of the data. Feedback was provided by NOAC for those areas where improvements would permit NOAC to use abstracts provided via this route. During FY 1990 and FY 1991, NOAC continued to explore the feasibility of adding LER abstracts for SCSS as supplied from the NUDOCS system. Programming efforts were j undertaken durtng FY 1990 to provide appropriate interfaces between SCSS and the NOAC base file which supported preparation ofthe LER Compdation(NUREG-CR 2000)under Job Code A9135. Beginntng in June 1992, LERs were downloaded directly from i NRC's NUDOCS system. Beginning in September 1992 LER abstracts and inventory records were extracted from the electronic downloads thus eliminating the need for entering abstracts via an OCR and manually entering inventory records.
l l
NRC Form 189 (64s) ,
NRC Form 189 (Continued) U.S. NUCLEAR REGULATORY COMMISSION JOB CODE (10-93) A9134 NRCMD 11.7 DOE LABORATORY PROJECT AND U^'
COST PROPOSAL FOR NRC WORK 08/21/96 PROJECT TITLE. Sequence Coding and Search System Routme processing of LERs continued for FY 1990 through FY 1995. No new types of data were mcorporated into SCSS.
Prior to May 1983. LERs were manually abstracted and keyworded by technical personnel to supply LER data once each month to the NOAC master tile used to support preparation of the monthly LER Compdanon. In May 1983, the abstracts were taken directly from the hard-copy LERs. and the keywords were supplied from the keycoding process via computer translation from SCSS-coded LERs to update the NOAC file each month. The kepords for the NOAC file continued to be produced from SCSS during FY 1991. This task w as completed in FY 1992, as electronic downloads of LER abstracts removed the need for keycoding, and the LER Compdation was discontinued.
Problems identified by NOAC and AEOD which presented coders with difficult choices were resobed. and appropriate rules were prepared under a previous task entitled Resolution of Coding Problems. This task was completed in FY 1992. All a:tivities assoc.ated with coding and QA hase been placed in Tasks 1 and The Coder's Manual was previously updated and matntamed as a separate SCSS task to reflect rule changes, code definition changes. etc.. which may have affected the consi:*eng and accuracy of the sequence coding. Such additions and changes were issued as amendments to be incorporated in the manual. Future work will be cosered Task 3-SCSS Dat: base Documentation.
Lb se, modifications to the SCSS Programmer s Manual were prepared as a separate SCSS task. This manual was published l in bytember 1985 to describe the computer softw are and operational procedures used to manage the SCSS database. Amendments to the manual reflecting additions and changes to the software and procedures were issued in September 1986 and September 1987 as Supplements ! and 2, respectively. No amendment / supplement was published for FY 1988. Supplement 3 was issued in September 1989 documennng the programming for the performance indicator (PI) analysis routine for cause codes. Work previously planned for completion in FY 1992 to document the conversion to the new JOSHUA software was halted in FY 1992. The transfer to the new JOSHUA software was not executed as the current version of JOSHUA was judged more efficient for SCSS needs.
Future work regarding updates of the Programmer 's Manual will be covered by new Task 3-SCSS Database Documentation.
2 The SCSS catabase application was transferred from an IBM 3090 computer system located at the X-10 site to a newer, more powerful IBM-compatible mGframe computer system located at the t-12 site late in FY 1993 as part of an Energy Systems effort to impros e computur sutem e'lieiency by consolidating some cornputer resources.
SCSS Utilization NOAC prepared the computerized output for the NRC LER monthly report starting with the January 1982 issue. NRC's LER file maintained on the National Institute of Health (NIH) computer system had been used to generate the LER monthly report previously.
This task was completed in FY 1992.
A task was added in FY 1990 to prerare special reports to AEOU on an as-requested basis on the results of major analyses and reviews ofindiddual plar%) performa.sce, such as plant operational experience reviews for input to AEOD Diagnostic Evaluations.
Beginning in FY 199J these special reports have been covered under Task 5-Technical Assistance.
Prior to FY 108? a task to maintain the SCSS User
- Guide was performed under this job code (A9134). In FY 1989, this task was associated with he Job Code A9135-Sequenca Coding and Search System Utilization. The most recent amendment was issued in Decemtur 1992. Additional work on the Ust r's Guide wil! be covered under SCSS Task 3-SCSS Database Documentation.
1Ggfevelonment Following the successful conversion of the SCSS database to the JOSHUA system in FY 1984, a number of refinements and modifications were made in the JOSHUA sottware. The JOSHUA sersion of the SCSS database was documented through the preparation of an initial draft of the User's Guide in January 1984, a revised dratt in May 1984, and a final report in August 1984.
NRC Fem '89 (6 9D , ,
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NRC Form 189 (Continued) U.S. NUCLEAR REGULATORY COMMISSION SOB CODE
{10 93) A9134 4
NRC M 11.7 DOE LABORATORY PROJECT AND DATE
- COST PROPOSAL FOR NRC WORK 08/21 96 Sequence Coding and Search System j PROJEC ' TITLE.
4
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A reference card was also prepared to assist users in accessing the database. Redsions to the controlled sersion of the User's Guide l J wers issued in April 1985. December 1985. Septemoer 1989. and C.:cember 1992. l
$ The software to maintatn and update the JOSHUA system was untten in early FY 1984, and the SCSS database was totally l converted from the DEC-10'1022 system in March 1984. Many software features have been deseloped and implemented to meet- 1
'i
, specific objectives and extend the searching capabilities of the system. Additionally, special applications programs have been i developed to proside NOAC statf with listings for qualits assurance (QA) purposes, missing LERs from inventory file. LERs remaming on the QA file LERs with incomplete data on inventory file etc. In FY 1985 additional software enhancements were 4 made. including the capability to search the inventory file. In FY 1986. software enhancements included commands to analyze LERs occurring during specified "wmdows" of time and the linkages of steps within LERs for potential common cause occurrences.
addition of coding rules as a separate. searchable file within SCSS, and upgrading the SINVENT command. No major improsements wcre implemented during FY 1987 through FY 1991. During FY 1992. programming efforts to utilize LER abstract j; and insentory tile data received electronically at NOAC were completed.
l NO AC conducted two trial runs in FY 1985 to examine the feas%ility and desirability of entering LER abstracts by means of an OCR rather than keypunching. During FY 1985, the system design for routing the OCR-read abstracts via the several computer.
systems to SCSS was finalized, acceptable type styles identified. and proposals made on modifying the LER form. NOAC began
- reading abstracts in via OCR in March 1986 and by May 1986 made the transition to utilizing the OCR as the primary means of entering LER abstracts. NRC issued Inspection & Enforcement Information Notice 86-06. providing guidance on specifications l on type styles, spacing requirements, etc., for utilities to follow in submming LERs to make the LERs more consistent with the OCR l requirements Use of the OCR as prtmary means of entry of LER abstracts has continued routinely since May 1986 through the end
- of FY 1992, when the LER abstracts were parsed from data received electronically at NOAC via NUDOCS.
j Work was initiated in late FY 1985 to develop the requisite software and procedures to permit direct. interactive entry of SCSS.
coded LERs by coders. In FY 1986 the development was completed and in May 1986 NOAC completed the transition and has 4
- ontinued to utilize on-line coding as the primary means of entering LER matrices.
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l A scoping study was conducted during FY 1989 to assess and evaluate an updated version ofJOSHUA (based on a current version j of FORTRAN). The study deternuned the overall impact on SCSS in terms oflevel of effort required, proposed schedules and costs i associated with the conversion. This report was submitted to AEOD in August 1989 and formed the basis for work during FY 1990 and continuing into FY 1991. During FY 1990, efforts consisted of converting the existing programs and subroutines to the new JOSHUA. writing new software when required, and adapting existing programs to operate under the new JOSHUA because of attferent operating and file handling characteristics as compared to the current version. A prototypic version of the new software was completed at the end of July 1990. This prototypic version served to demonstrate the feasibility of using the new JOSHUA for managing and searching the SCSS database. The conversion to a new IBM 3090 computer was made in September 1990. During l FY 1991, efforts focused on converting all procedures associated with updating the database. Essentially two systems were maintained for several months. A transition to the updated JOSHUA was postponed due to (1) inefficiencies inherent in the new JOSHUA that resulted from its requirement to operate on multiple machine types; the current JOSHUA is designed specifically for IBM machines and incorporates efficient, IBM-specific inputeoutput routines and (2) the feasibility of a workstation-based system replacing the mainframe-based system with the potential for substantially reducing the long-term cost of operating the database.
A letter report documenting the status of the conversion to the new JOSHUA was sent to AEOD in March 1992.
NOAC initiated efTorts in FY 1990 to etTect a direct transmission of LER abstracts from NRC's NUDOCS system to NOAC for adding to the SCSS-coded matrix. Tapes were provided initially to NOAC from NUDOCS but proved difficult to use because of inconsistencies in the format of the data and with the quality of the data. Equipment and data lines installed by NRC telecommunications personnel initially thought to provide a direct link to NOAC as a node on a network with NRC Region !! and the Institute of Nuclear Power Operations (INPO) were not compatible. Efforts during FY 1991 and FY 1992 centered on identifying other methods or networks for providing this link. A link was established in FY 1992 by establishing a NOAC account on the NRC's NUDOCS computer system and transferring LER data files to NOAC on a weekly basis. Parsing routines were 6@W f - se.> 9 9 Q *s C E s - - ^- ^^
I NRC Form 189 (Continued) U.S. NUCLEAR REGULATORY COMMISSION JOB CODE
' A9]34 (10 93)
NRCMD 11.7 DOE LABORATORY PROJECT AND U^
COST PROPOSAL FOR NRC WORK 0801 96 PROJECT TITLE. Sequence Coding and Search S,sstem developed late m FY 1992 to retnese mformanon from the downloaded files sufficient to supply the SCSS inventory file a abstracts required to complete the coding record. The use o. electronically supplied LER data substanually reduces the required to prepare an SCSS data record.
During FY 1991, the development of a beta (test) sersion of the SCSS Front End Processor ( FEP), a PC-based menu-d for SCSS. was completed, a user's guide was prepared, and a training class for test users was held for a group of selected use test the software. Feedback from the test users was obtained during FY 1992 and was documented in Test Permd Craluatwn of SCSS-PC: The Sequence CoJmg and Search System Database Front-End Processor. prepared in April l992.
A scoping study completed in FY 1992 concluded that it is feasible to operate the SCSS database on a smaller, more platform (workstation) with more intuitise user-friendly software than the existing mainframe system. A follow-on task w initiated to etTect the transition to a workstation-based platform. .\ program team was assembled in FY 1993 to prepare a detailed program plan to guide the transition to the workstation-based s,sstem. The program plan was submitted for AEOD re 1993 and then modified in early FY 1994. The program plan then underwent a critical review by AEOD statrand a subcontractor (ORTech), was modified. approved. and then implemented. Consistent with the program plan. SCSS requirements were documented. logical data models deseloped, process model requirements established and in the process of being deve a procurement request prepared for purchastng appropnate hardware and sorlware to develop the enhanced SC
- application. The program plan was modified m FYS 1995 and 1996 to reflect improvements in web-based techno issues.
l Additional information Task 1-Routine Codine and Addition of LERs to SCSS File. Routine coding ano addition of codable LERs continued for FY Approximately 1,400 LERs (including revisions) were added to SCSS during FY 1995.
Task 2-Ouality Assurance Procram for Codine and Processine LERs. The QA program was carried out during FY 1995
- with the procedures contamed in the QA Afanual as modified by Revision 3 of the document. Revised vers ,
were transmitted to AEOD in October 1984, January 1985, April 1985, September 1985, and November 1985. RevisioI QA Afanual was issued in April 1986 desenbing the on-line coding of LERs and OCR entry of LER abstra Amendments 2 and 3 were issued in April 1987 and October 1987, respectively. No amendment was issued for FY 19 Revision 2 of the manual was completed in July 1989, updating the frequencies with which QA tasks are performed J
individuals responsible for each task. Amendment I to Revision 2 was issued in September 1990. Revision 3 of th l issued in September 1991.
Task 3--SCSS Dattbase Documentation. All database documentation activities will be consolidated Task 4-Respondine to Inouiries and Utili7ation of Data. NOAC staff continued to respond to information requests d by performing searches of the SCSS database and direct interaction with AEOD, other NRC personnel, and N )
Task 5-Technical Assistance. NOAC provided technical assistance involving evaluations of operating experienc j
searching SCSS to develop programmatic performance indicators, and providing results for complex se l sequence for loss-of-coolant accident scenarios.
Task 6-NRC StaffTraininc. Dunng FY 1994, five presentations on the use of the SCSS database via the SCSS F were held at the NRC regional offices and at the NRC headquarters in Rocksille. The Rockville presentation l to facilitate LAN installation and operation of the Front-End Processor software.
uc re- ses +95) PAGE 9 OF 23 _
NRC Form 189 (Continued) U.S. NUCLEAR REGULATORY COMMISSION JOB CODE (10 93)
A9l34 NRCMD 11.7 DOE LABORATORY PROJECT AND U^I COST PROPOSAL FOR NRC WORK 0801'96 PROJECT TITLE Sequence Coding and Search System Task MCSS Workstation Conserdon. This task to begm the transition to a workstation-based SCSS platform was proposed for FY 1993 and formally initiated in FY 1994 under Job Code A9451. This task will be carried out under Job Code A9134 through FY 1997.
Task 841ainframe-Based Front-Fnd Processor I'r$ dates. During FY 1994. AEOD expanded the use of the SCSS database primarily sia the FEP and requested support to facilitate its use. This task uas formally carried out under Job Code A9451, but will be carned out under Job Code A9134 in FY 1995 and later.
Task 9 ORNL/INEL LER Database Consolidation. NOAC examined the feasibility of consolidating LER processing activities at ORNL so that multiple, labor-tntensive LER reviews may be reduced to a single LER res iew and subsequent data entry of LER data sufficient to meet AEOD. INEL. and NOAC LER data requirements. This examination was documented in a October 1994 report to AEOD. The consolidation of LER processing activities does indeed aprear feasible. This task was formally carried out under Job Code A9451, but will be carried out under Job Code A9134 in FY 1995 and later.
Task 10-SCSS Common Cause Failure Anahsis. During FY 1994. NOAC implemented SCSS search strategies to identify common-cause failures and added the capability to also identify independent failures for many systems components identified by AEOD. This task was formally carried out under Job Code A9451. bu:
- ill be carned out under Job Code A9134 in FY 1995 and later.
- 3. WORK TO DE PERFORMED AND EXPECTED RE5ULTS:
For FV 1996, the work for each of the 1 I active tasks (Tasi.s I-l1) is:
Task 1-Routine Codine and Addition of LERs to SCSS File. NOAC shall code all nonenvironmental LERS reported to the NRC by all commercial nuclear power plants except Ft. St. Vrain. These LERs shall be coded using the latest rules, procedures, and system descriptions either contained in the SCSS Ceder's Manualor those approved and awaiting addition to the SCSS Coder's Manual. The LERs shall be added to the SCSS production file within two weeks of receipt by NOAC. NOAC anticipates receiving 1,400 LERs and LER revisions for each year during the performance period. Processing statistics for LERs received and added to the database will be provided'in monthly progress reports.
P1 cause and corrective action codes wiil be identified for each LER in conjunction with the SCSS coding process. Cause codes will be assigned based on engineertng judgement. A cause code search algorithm, which identifies steps that include potential P cause codes for individual steps, will be executed to serify assignment of ecdes. A PI corrective action code is also assigned based on explicit information reported in the LER.
P1 data will be transmitted electronically and'or on disk in dB ASE 111 fomist to AEOD or their subcontractors on an as-requested schedule, approximately six times per year, to support preparation of NRC's PI report. The information to be included in th transmittal is to be provided on a plant-by-plant basis listing the LER nt mber, event date, docket (s) afTected, and the cause co and corrective action codes assigned.
LERs will be downloaded via a direct link with NUDOCS. LER abstracts and inventory records will be compiled from these l
downloads. NOAC will also receive a paper copy of the LER through the usual mail distribution system.
Task 2-Oualitv Assurance Procram for Codine and Processine i ERs. NOAC shall contmue to implement a QA program for assunng the accuracy and consistency of coded LERs. This program is desenbed in the report entitled Sequence C l
System Quahrv Assurance Program. ORNL/NOAC-225, Revision 3 (September 1991). The QA program for FY 19 represents some changes from the QA Manual. It includes. but is not limited to. the following items:
oc wms, g g, g
NRC Form 189 (Contmued) U.S. NUCLEAR REGULAMY COMMISSION JOB CODE l I
(10-93) A9134 I NRCMD 11.7 DOE LABORATORY PROJECT AND U^I COST PROPOSAL FOR NRC WORK 08/21 96 PROJECT TITLE. Sequence Coding and Search System a Up to apprournately 15 to 208. of all coded LERs shall be completely resiewed by another techmcal processor, depending upon the significance or complexity of the esent.
- b. All coded LERs that are not QA reuewed (80 to 85'.) will be scanned to identify errors m coding mechanics (appropriate fields completed. unusual component-s> stem pairs. etc.) before they are added to the database.
- c. Computerized checks for validits of codes, completeness in coding, and enforcement of rules shall be performed on all coded LERs interactively at all three phases of processing. Work to identify and implement additional computer QA checks shall be ongoing. Each QA check will be discussed with AEOD prior to implementation.
- d. Quarterly group QA meetines shall be held to provide continuous training for SCSS staff and to identify problems or inconsistencies in coding practices. Unusual LERs in w.iich codir.g does not exactly follow a p edefined rule (not to exceed l*6) will be discussed. This discussion traming will tend to establish consistency in coding philosophy in addition to promoting the deselopment of additional rules. Meeting topics that result in new guidelines will be included in the monthly status reports for AEOD approval.
- c. A brief editorial review of all abstracts added to the SCSS and NOAC databases will be performed.
- f. Monthly statistics shall be nauttained and plotted on the number. type, and significance of changes made during QA resiew of coded LERs and form scan. The SCSS staff will be made aware of these statistics, which are compiled for each SCSS statT person, at the Q A meetings. These statistics shall also be used to identify when the percentage of LERs that are QA reviewed for a particular technical processor should be increased or reduced. The statistics will be related to error control points for inclusion in the monthly status reports. l l
- g. An annual audit shall be conducted of the inventory file to ensure that the database is complete. NOAC shall identify and re all LER numbers which have a questionable status (i e.. LER numbers for which neither an LER nor a cancellation lettet has been received, but w here at least one LER with a higher sequential number has been received). NOAC shall utilize results of simiir audits of LERs performed by the Idaho National Engineering Laboratory for AEOD for the P! program to ensure completeness.
- h. One enluation of the QA program (in-depth audit) shall be conducted where 50 LERS are QA reviewed a second time to evaluate th' QA review and scan operations. The results of this annual review will be included in a monthly status report.
- i. NOAC will continue to identify new QA checks as new coding rules are established and develop computer programs to perform these checks in support of automated coding serification. Each QA check will be discussed with AEOD prior to implementati
Task bSCSS Database Documentation. The following SCSS documentation will be updated as directed by AEOD when significant changes have been identified:
I
- a. Coder's A1anual
- b. Programmer's Afanual
- c. User's Guide
- d. QA Program Afanual
- e. Front-End Processor Afanual
- f. SCSS On-Line HELP Files
- g. Future SCSS Conversion Documentation QRg Form 9 t'9 ss-95 9ACM (LD ?W '3
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NRv Form 189 (Contmued) U.S. NUCLEAR REGULATORY COMMISSION JOB CCCE 7 i (10 93) A9134 f l NRCMD 11.7 DOE LABORATORY PROJECT AND DATE 8 l
i COST PROPOSAL FOR NRC WORK 08/21 96 l !
PROJECT Tl7LE. Sequence Coding and Search System The deselopment and distribunon of imual Jocumentauon associated with the 5 CSS workstauen consersion t Task 7 will be performed as part of that task.
In addition to the abose. NOAC will produce a one-page. two-sided newsletter for quarterly distribution to SCSS users to inform I them of coding rule changes and to proude a medium to support conunued training for the users. Possible uses of the newsletter . j I
include explaining new features as they are added to the database. sharmg the results of searches of potential interest to NRC statf.
and prosiding example searches to illustrate database searching capabilities. A drati of the newsletter will be provided to the AEOD project manacer for resiew prior to distribution.
NOAC will mamtain a marked up draft of recommended changes for each manual. Costs associated with documentmg these chances will be allocated to the task associated with the change. For example. if the development of a new coding rule resulted from a QA meeting. associated costs for the draft mark-up of the LoicC knni will be allocated to Task 2-Quality Assurance Program for Coding and Processmg LERs.
Task t-Restsondinc to Inouiries and l'tilization of Data. NOAC shall respond to requests for special searches, source documents.
consultations and inquiries from the NRC. The requests must be related to operational experience information or to data available on the SCSS and/or other NOAC databases. NOAC shall tabulate the requestor's name and affiliation the request date, the subject l
area of the request the database searched. the approxirnate time required. the response date, the results of each special search or l request for information, and any costs billed for cost recosery searches. Thi.s information shall be reported in the monthly progress i report. All letters transmitting search results shall be resiewed by a second individual (a) to verify that search strategies used are correct and consistent with the request and (b) to ensure that all printouts are complete. The NRC project manager will receive a copy of search results transmittal letters. Approstmately 170 exempt requests are anticipated each year during the performance period.
l Task 5-Technical Assistance. Durmg the cour:e of this project. technical assistance on specific problems covered by the scope of work described herem may be needed. These efforts are high priority, quick-turnaround tasks of a short-term nature and may only be assigned by the NRC Project Manager. All requests reqaire a brief written assistance description. Approximately 3 requests are l
expected each year of the period of performance. Each report is estimated to require approximately one staff month of effort. The impacts on the costs or schedules of other compenng AEOD work (either with;n or outside of this project) will be discussed with the NRC . Project Manager.
l After completion of each of these efTorts, a letter shall be submitted to the Project Manager and others designated by the Project Manager which contams a brief summary of the work performed and the actual costs. This letter is in addition to any technical reporting requirements. In addition, monthly letter status reports shall include a complete compilation of all assistance requests received during the month stating the request, the requestor, date of request, status (including completion date, if applicable) and the cost.
Task 6-NRC Staff Trainine. NOAC shall develop an SCSS information package suitable for making present tions to inform NRC staff of the capabilities of SCSS. In addition. six training courses of about six hours each will be presented at NRC facilities for new SCSS users. Efforts on this task will be performed when directed by the AEOD Project Manager.
! Task 7-SCSS Workstation Conversion. A scoping study completed in FY 1992 concluded that it is feasible to operate the SCSS database on a smaller, more economical platform tworkstation) with more intuitive, user friendly software than the current
' mainframe-based system. This task implements the conversion of the SCSS database to a workstation-based system that provides these benefits. A comprehensise project plan was developed in FY 1993 and subsequently modified, resubmitted, and approsed by AEOD in FY 1994,' FY 1995, and FY 1996, and is being implemented through FY 1997. The approved project plan documerits decision points milestones and major deliverables, and cost and work schedules that will be used to govern this task.
W & " 9 + 9st . _ _ _,, .,,, _
NRC Form 189 (Continued) U.S. NUCLEAR REGULATORY COMM'"SION JOB CCDE A9134 (10 93)
NRCMD 11.7 DOE LABORATORY PROJECT AND U^I COST PROPOSAL FOR NRC WORK 08Cl.96 PROJECT TITLE Sequence Coding and Search System The plan includes subtasks to plan and manage the project. provide a conceptual design for insights and comment. recommend and purchase development harduare and software. and define SCSS requirements on the new platform. It also includes subtasks to identify and purchase production hardware and software for long-term. workstation-based operation; design and build the new database; document, validate. and verify the new system, and develop and provide training to NRC statT. This task was initiated under Job Code A9451. It was performed based upon the approsed project plan under Job Code A9451 until funding for that job code was depleted. The work was then contir.ued under Job Code A9134. The funding estimates provided for this job code are for the portions of these tasks performed under Job Code A9134.
Task 8-Mainframe-RaseJ Front-End Processor Updates. During the period of performance, recommended enhancements to the FEP may be expected based upon feedback from the expanded user group. Upon written authorization from AEOD NOAC will continue to develop and refme the FEP to incorporate these enhancements within funding amounts for this task. This task was initiated under Job Code A9451. It was performed under the guidance provided in Job Code A9451 until fundtng for thatjob code was expended. The work was then continued under Job Code A9134. The funding estimates provided for this job code are for the ;
j portions of these tasks performed under Job Code A9134. Since the workstation sersion of the SCSS database is expected to be i operational by calendar y ear 1997, no work is planned for this task.
Task o-ORNL4NEL LER Database Consolidation. NOAC examined the feasibility of consolidating LER processing acuvities at ORNL so that multiple, labor-intensive LER reviews may be reduced to a single LER review and subsequent data entry of LER data sufficient to meet AEOD INEL. and NOAC LER data requirements and documented the examination in a October 1994 report to AEOD. The consolidation of LER processing activities does indeed appear feasible; thus, a project plan to address the consolidation will be prepared upon authorization by AEOD. Major issues will be identified including: staff training, data conversiorutransmission routines, processing 50.72 data, and constructing a consolidation schedule consis.ent with the conversion ofSC99 to a workstation-based database management system. This task was initiated under Job Code A9451 but will be completed under Job Code A9134. No work in FY 1996 and beyond is anticipated for this task.
Task 10-SCSS Common Cause Failure Analvsis. NOAC will perforrr searches for common cause failure and independent failure events for designated components and systems using SCSS. The searches will be conducted using the algorithms deeloped for l
this purpose in prior years. The search results will be two files, one for common cause failure events and one for independent failure I events, containing the coded step matrices and the LER abstracts for the events. This file will be transmitted to the INEL for review and inclusion into the CCF database. The AEOD project manager ' vill provide a schedule for completing the searches. A letter report will be prepared to document the search strategies and results. Development of search strategies was completed in FY 1995; therefore, searches for this topic will be conducted under Task 4 and no work is anticipated for this task in FY 1996 and beyond.
This task was initiated under Job Code A9451. It was performed under ".e guidance provided in Job Code A9451 until funding for thatjob code was depleted. The work was then continued under Job Code A9134. The funding estimates provided for this job code-are for the portions of these tasks performed under Job Code A9134.
Task 'l-Technical Assistance to Smoort an Indeoendent Safety Assessment. This task is for the performance of reliability and risk-based analysis of selected systems and testing support evaluation as part of an Independent Safety Assessment (ISA) team at the Maine Yankee nuclear power plant. Being pan of the ISA team, this work will be conducted primarily at NRC and Maine Yankee facilities. The task, to be performed by a probaLlistic risk assessment (PRA) expert, consists of several elements.
c
- a. Prepare a plan for evaluating testing and for performing reliability and risk based analysis of system performance of at least two plant systems (auxiliary feedwater and one other system to be determined). The plan will also include risk-based e key issues / scenarios identified by the inspection. The overall Evaluation Plan (provided by the NRC) can be used as a gu since it will outline the areas to be evaluated. Licensee background and technical information shall be reviewed to ensure that this plan covers all required areas.
HRC Form 16916 9s) paGE 13 OF 23
NRC Form 189 (Continued) U.S. NUCLEAR REGULATORY COMMISSION l OB CCDE ,
(10 93) A9134 '
1 I
NRCMD 11.7 DOE LABORATORY PROJECT AND DATE COST PROPOSAL FOR NRC WORK 08 m 96 f t
PROJECT 9TLE Sequence Coding and Search Sy3 tem
- b. An initial sisit of about two weeks to the licensee facihty is planneJ and shall .oncentrate on information gathering mcludmg an esamination of the licensee's actiuties an J performance m specific areas. The esamination shallinclude interuews uith key licensee personnel at all lesels. programmatic resiews and assessments. reuews of selected safety systems. maintenance component failure and asailabilits data. and direct obsenations Esaluation methodologies include a quantitative esaluation of risk associated with selected systems. testing erTectiseness and reconciliation of testing. and design basis requirements-discrepancies.
- c. Following the initial usit to the licensee facihty. approumately two weeks are scheduled to further esaluate and salidate any obsenations, brief NRC management on preliminary findings. and refocus or redirect the esaluation as appropriate.
- d. Another tuo week usit to the hcensee facihts will be used to remforce prehmmarv tindtngs to perform a special case study saluation of specitic issur areas. and estabbsh and sahdate root causes
- e. A final repon shall then be prepared This repon shall contain the resuits of the mformation gathenng and anal) sis relatec to actn itie; desenbed abose. This report will be utilized by the NRC Mamtenance and Testmg Team Leader as input to the final ISA report. All predecisional data shall be returned to the NRC Project Manager upon the completion of the report.
- 4. PROPOSED PERSONNEL-INCLUDE RESUMES:
l W. P. Poore Program Manager responsible for planning, admmistration. and reporting. Additionally, he proudes technical contributions to all tasks.
D. T. Cannon Serves as Principal investigator for Task 7.
R. F. Christie Provides technical contnbutions to Task i 1.
W. E. Kohn Lead engmeer for tasks ins ching the analysis and esaluation of plant performance (Ta<k 5).
R. J. Belles Prosides technical contributions to Task 5.
J. L. Hardee Database deselopment speciaHst to be used for Task 7.
K. M. Johnson Prosides technical contnbutions to all tasks.
B. King Database development specialist to be used for Task 7.
A. J. Martellaro Database development specialist to be used for Task 7.
l C. M. Mitchell Provides technical contnbutions to Task 5.
D. F. Nawrocki Provides technical contnbutions to Task 5. j J. J. Rooney Provides technical contributions to Tasks 1-6 and 8-10.
J. A. Farquharson Provides technical contnbutions to Tasks 1-6 and 8-10.
l L. E. Palko Provides technical contnbutions to Tasks 1-6 and 8-10.
i H. Paula Provides technical contributions to Task 10.
(Resumes are attached).
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- 5. MEETINGS 4 RAVEL: l
. l To meet the objectives of this project, ftu..s for domestic trasel hase been specirled It is anticipated that two statTmembers will travel once annually to AEOD otlices in Rocksille. MD for one day of Program Resiew meetings for each year of the performance period.
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I NRC Form 189 (Continued) U.S. NUCLEAR REGULATORY COMMISSION s0B CODE (10 93) Ag[34 NRCMD 11.7 DOE LABORATORY PROJECT AND U^'
COST PROPOSAL FOR NRC WORK 08/21.96 PROJECT TITLE. Sequence Coding and Search System Approximately six trips for one person for one to two days each are anticipated to provide traming to NRC region and headquaners staff on the workstation-based SCSS sy stem during FY 1997.
It is also anticipated that four trips to Rockville. MD and two trips to Brunswick. ME. will be required to support Task 11. The travel is anticipated to require 29 days per diem in Rockville and 24 day s per diem a Brunswick.
- 6. NRC FURNISHED M ATERI ALS:
Licensee Event Reports will be provided to NOAC via (1) electronic download from NUDOCS and (2) hard copy f om the NRC's Regulatory Information Distribution System. The data from NUDOCS is the primary data source; the hard copy LERs are I supplementary. Performance monitoring of LER coding activities will be based upon the receipt of f ERs from NUDOCS. j l
AEOD will maintain NOAC's electronic access to 50.72 data.
The NRC will provide necessary background information such s beensee organization charts. inspection reports. safety program descriptions or other material' guidance specitied by the NRC leader for the Task Ii support.
7 RELATIONSHIP TO OTIIER PROJECTS:
In FY 1983, the SCSS project was divided into three segments: LER Utilization ( A9135), Sequence Coding and Search System Development ( A9451), and Sequence Coding and Search System Operation ( A9134), w hich is the work described in this proposal These three job codes for SCSS activities remained separate until Job Code A9135 was subsumed by A9134 in FY 1994 and Job Code A9451 was subsumed by A9134 in FY 1995.
This project is also integrated with Job Code 80435 (LWR Accident Sequence Precursors), since the ASP program utilizes a screening of LERs via SCSS to identify potential precursor events.
- 8. REPORTING REQUIREMENTS AND SCllEDULE:
Monthlv Progress Report NOAC will prepare a monthly business letter status report in accordance with the current NRC Management Directive MDI 1.7 and NRC Project Management requirements. The report will be received by AEOD by the 20th day of the following month. This report ;
willinclude the following items:
- a. ~ Reporting requirements as identified within the task descriptions. .
1
- b. An SCSS Processing Costs Graph reflecting the following monthly statistics: (1) quantity of LERs coded, (2) $/LER, and (3) hour /1.ER.
- c. Estimates of subcontractor charges corresponding to subcontractor effort for the reporting month. j
- d. A graph which plots projected cumulative costs over time against actual cumulative costs over time. Projected cumulative costs are for expected expenditures during the fiscal year, exclusive of carryover into or out of the current fiscal year.
- e. Estimates of DOE charges to ensure the monthly status report accurately reflects the total expended funds.
- f. Plans for the next reporting period for nonroutine, ongoing etTorts. A discussion of the work to be performed and milestones which will be completed during the next period will be described.
L NRC Fem '?9 f6 95) ~~ cn nry u
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I NRC Form 189 (Continuea) U.S. NUCLEAR REGULATORY COMMISSION .CBC00E ;
I (10 931 -\ 91.M .j l NRCMD 11.7 DOE LABORATORY PROJECT AND DATE I l COST PROPOSAL FOR NRC WORK og 3 on t l l PRO.,ECT ~;TLE Sequence Udine and Search Sutem l l J A Jetailed hstm; of all m ;u:r:es r,cenej Juring the month including (ne reo;uestor s name and affilianon. a brief Jescripuon 0 the sucject matter. results ana teta! labor hours espended by %AC and succontractor personnel to aJJress the inquiry The grand total ofinquiry labor nours uill be iJentified
- h. SCSS database usage tables willidennf) actne user accoums with monthly and year-to-date usage of the catabase.
- i. A fee-recosery section uhich idennties charges and paymer.ts for cost recosers searches for requestors outside the NRC.
Performance indicator Data PI data will be transmitted electrut aally and or on disk in dB ASE 111 format :o AEOD or tne.r subcontractors on an as-requested schedule tapprostmately six times per seats to support preparation of NRC's biannual Pl tcport The information to be included m the transmittalis to ce prouded on a plant-by-plant basis h>tm; me LER number. esent da:e. docken si arrected. and the cause codes and correctne acoon coJes assigned iTask i t Renorn to be issued in FY 1006 and FY loo"
- a. Amendments uill be prepared as requested to update SCSS documentanon i Task .h I
- b. Letter reports and technical studies and anal)ses resulung from searcnes of the SCSS database i Tasks 4 and 5 ). I
- c. Structured SCSS capabilities presentations in addition to user traming along with associated documentanon t Task 6).
- d. Seseral milestone reports are identified for Task '-SCSS Workstation Conversion and noted in the approsed project plan.
- e. Front-End Processor upgrades uill be delisered upon request iTask 8).
f An LER Consolidanon project plan will be prepared and delisered upon AEOD's request.
- g. Common cause failure search results will be deinered upon request. l
- h. A draft report documenting e! Torts on Task 11 will be prosided to the NRC Maintenance and Testing Team Leader at the completion of the evaluanon as input to the final ISA report.
l WC F:- 'es 6 95' ,, , , _ _
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- l NRC Form 189 (Contmued) U.S. NUCLEAR REGULATORY COMMISSION l JOB CCCE (10 93) A91.4 NRCMD 11.7 DOE LABORATORY PROJECT AND U^'
COST PROPOSAL FOR NRC WORK 084,196 PROJECT TITLE Sequence Coding and Search Sprem 9 SUBCONTRACTOR,CO.NSULTANT AND M AJOR PROCUREMENT INFORM ATION:
A. Subcontractor / Consultant:
The AEOD Project Manager will be notified prior to entenng mto any techmcal sersice subcontracts not identified herem Cost Estimates (SK)
Description and Justification FY 1995 FY 1996 FY 1997 FY 1998 Subcontractors:
JBF Associates Direct Labor M O O Technology Drise Trasel e e e 1000 Technolocv Park Center Os erhead W W Knouille. TN [7922 Fee . M Q Toul 205 l i '- 243 42 Subcontractor statTis used to complement ORNL expertise m several areas: coding and QA of LERs. assist in aspects of plant <
reviews, and support SCSS common-cause applications. The subcontractor selected has special expertise or experience in its !
respective areas to complement ORNL staff. Approximately 4 i FTE of subcontractor assistance is anticipated for FYs 1995-1998. [ Subcontractor resumes are attached.]
B. Capital Equipment:
Prior to closecut of a project, a reconciled report will be developed by DOE ta record available equipment and material purchased with NRC funds. The report should contain the MOU Property description or nomenclature, manufacturer, model number, serial numoer. quanaty, acquisition cost. receipt date. condition code, and DOE or contractor property identification number. The repon shall also identify any ongoing or contemplated NRC projects on w hich the MOU Property could be used. If no MOU Property )
is assigned to the project, the DOE shall provide a negative report. Any MOU Property requiring special handling for security, health, safety, or other reasons shall be noted as part of the report. This report should be submitted as soon as possible after a project completion or termmation decision has been made, but not later than 60 days after the termination date. The report should be submitted to the applicable NRC otTice. ATTENTION: Program Suppon StafT. ;
i Prior to purchase of property with NRC funds. DOE shall conduct utilization reviews of DOE and other appropriate sources of unrequired, excess, and surplus property. Property identified during these reviews that meet NRC project needs shall be transferred to the project in lieu of purchase. DOE shall monitor MOU Property assigned to the project on a regular basis to identify unrequired MOU Property. Unrequired MOU Property shall be reported to NRC for utilization screening using the procedures followed for MOU Property disposal at project closecut.
C. Major Procurements:
A more powerful web server may be required for the future as more NRC start use the web version of the SCSS database beginnmg in early CY 1997. The potential purchase of this more powerful computer is included in this proposal.
oc e- 99 +95) y
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d NRC Form 189 (Contmued) U.S. NUCLEAR REGULATORY COMMISSION JOB CODE 1 (10 93) A9l34 j NRCMD 11.7 DOE LABORATORY PROJECT AND DATE
< COST PROPOSAL FOR NRC WORK 08m %
q l
PROJECT TITLE Sequence Coding and Search Sprem i
3
. 10. SPECIAL FACILITIES. lF REQt' IRED:
- The purchase of a computer hardware and software system to operate the SCSS database and repbce the current mainframe-based j SCSS sortware is anticipated. Current projections are for a serser sy stem and corn.mercial .,ottware. The cost of the hardware and I i
- sottuare system is estimated at $120K. ( Approstmately 540.K of this amount uas expended under Job Code A9451.) The estimate
- is dependent upon the exact sy stem requirements uhich at this pomt hase not been specified. The purchase of equipment required for the performance of work under this job code requires the prior approval of the NRC project manager and is not budgeted for in this proposal.
J
- 11. CONFLICT-OF INTEREST INFOR31 ATION:
i There are no known relationships between this organization or its emplo,.ees with industries regulated by the NRC and suppliers j thereof that might gis e rise to an apparent or actual contlict ofinterest regarding the work described in this proposal.
ORNL has a letter in its files from JBF Associates which indicates that the abose statement is also salid for this organization.
I
- 12. CLASSIFICATION OR SENSITIVITY. IF APPLICABLE (e g., safeguards, proprietary, other): l l
NOAC shall develop a securits p;an consistent with NRC NIanagement Directise i1.6 to protect proprietary LERs to be provided to NOAC before they are made asailable for searching and retneved by appropriate NRC statTand contractors.
- 13. ADPrNDU31:
(A) Interpretations of Stateme~ J Work -
The quality assurance progran. . oding LERs is included as a separate task (Task 2) and is discussed in Item 3-Work To Be Performed and Expected Results. j NOAC shall adhere to the guidelines for the database management system software described in (1) Quality Assurance Workbook: A Guide to the Development ofPfarufor Project Quality Assurance. KiDSRD-420:R1 and (2) Mission Success:
A Qualsrv Assurance Program Descr prionfor the Data Systems Research and Development Program. KIDSRD-424Rl.
The project management plan will serse to docurnent the QA activities associated with this task. The reports produced to complete the various subtasks will serve as reference documents for quality assitrance purposes. QA activities will be commensurate with subtask requirements and implemented with the concurrence of the AEOD Project Manager.
Software development. modifications. or maintenance tasks shall follow general guidance in NUREG/BR-0167. Software Quality Assurance Program and Guidelmes. and specific guidance designated by the AEOD project manager.
Part VI!! (B)(3) of NRC Management Directive Handbook i L7 *equires DOE operations offices to report software system information and laboratory costs incurred during the fiscal year on an annual basis to the NRC Office of Information Resources Management for NRC-titled sottware that has an initial development or acquisition cost of $25,000 or niore and j has a useful life of two or more years. To comply with this requirement. DOE laboratories shall track and report software acquisition costs and software development costs for each system until the software becomes operational. If NRC-titled software systems are still under development when the annual report is compiled by the DOE operations office at the end of the fiscal year the laboratory shall so annotate. The report shall also indicate software systems that are operational if deliverables are provided on diskettes, then the diskettes shall be scanned for siruses and venfied to be free from viruses prior to delivery to the NRC.
NRC Form 959 (6-9s) ,,_ g y
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' NRC Form 189 (Continued) U.S. NUCLEAR REGUU10RY COMMISSION JOB CCCE (10 93) 1913.;
NRCMD 11.7 DOE LABORATORY PROJECT AND DATE -
COST PROPOSAL FOR NRC WORK 08,21 96 i
! I PROJECT TITLE Sequence Codine and Search Sutem ;
l I
i 13. (D) Cost information 1 Estimated Cost Schedule ISK)
Prior Years 1945 1996 1997 1998 Total I i
i TashI 8.118 636 n39 663 167 510.223
. Tash 2 2.336 81 106 l'0 43 52.736 Tash 3 13 1 0 48 12 574 Task 4 25 49 29 94 23 5220 Ta.sk 5 39 28 42 67 17 5193 l
]
Task 6 I I o I* 4 523 j
! Tash
- O 16? 4Ii 185 0 5763 1 1
, Task 8 o 5 0 0 0 55 1 Tash 9 0 9 0 0 0 59 l Tash 10 0 o 0 0 57 I l
] Task !! 0 0 56 19 0 575 Preu ju uv Completed Tasks '91 0 0 0 0 5791 l Subtotal $11.323 5984 $1.233 51.263 5266 515.119 DOE Added Factor fincluded in task subtotals for FY 1995 and earher: DAF waned for FY 1996 and bey ond) l
! TC tCostsi 511.323 5984 51.233 51.263 5266 515.119 l Carryoser from Prior Year 462 694 389 266 i Carr>oser to Nest Year 462 694 389 266 0 ,
I Total ifundinci 511.785 51.216 5978 51.140 50 515.119 l 1 l t
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d NRC N '8916 951 , ,,,,, ,,
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NRC Form 189 (Continued) U.S. NUCLEAR REGULATORY COMMISSION JCBCCCE l
, (10 93) A9131 NRCMD 11.7 DOE LABORATORY PROJECT AND 8 DATE COST PROPOSAL FOR NRC WORK J-082196 f PROJECT TrTLE Sequence Coding and Search Sptem
- 13. iC) s chedule information Subtask / Milestone Schedule FY 1994 FY 199A FY 1999 FY 1994 FY
)
BEYONO l SubtasktMilestone ;,g3g, , ; , j3j, ,j,l3g, , ; , j3;, ,j,l3 ., ry
]
Task 1 Reutine CoJing and Addition et LERs i to SCSS File
- Task 2 Quality Assurance Program for Coding i and Processing LEIO i
.I j Task 3. SCSS Database Documentation
. Taak 4 ResponJing to inquines and lit:ht.ation ol' D.ita T.dk $ Technical Assistance Task 6 NRC Sta!T Trammg l Tast ? SCSS Workstation Conserstion 'S
.\
- Task 8
- .\tamnmw Based Front End Processor Updm.; , .
I Tash 9. ORNLINEL LER Database Consolidation
! '1 Task 10. SCSS Common Cause Failure Analysis t-Task 11- Technical Assistance to Support an p b independent Safety Assessment i
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JOB CCOE EC Form 189 (Part 3) U.S. NUCLEAR REGULATORY COMMISSION (10-93) .\9134 l l NRCMD 11.7 MODIFICATION NUMBER
- 14. SPENDING PLAN: " accucac<ei ll l
FY 1996 0 l l
NAME OF LABORATCRY pppp p l
FROM TO l Oak Ridge National Laboratory ,
10/l.94 12/31 9' l Total estmatec costs )
TITLE OF PROJECT 1 of the proposed moofcation at tne SK 3 796*
Sequence Coding and Search Sy stem trne of preposal suemission I
ESTIMATED COST AND COMPLETION BY MONTH COST ELEMENTS OCTOBER NOVEMBER CECEMBER JANUARY FEBRUARY MARCH 1
DIRECT COST (SK) l
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INDIRECT COST (SK) 41 109 80 73 122 88 TOTAL CC"($K) 34
- 37N 3E'A
$MPLETION (%)
hb5W
-_m l
ESTIMATED COST AND COMPLETION BY MONTH l
april MAY JUNE JULY AUGUST SEPTEMBER COST ELEMENTS 186 122 121 145 120 76 DIRECT COST ($K)
INDtRECT COST ($K)
TOTAL COST ($K) 50 % $3% $7% 60 %
41 '. 6 O PL TION (%)
' Cost esumates pertain to the October 1.1995, through December 31.1997. penod.
NAC Form 189(6-95) i ._ ._, -- .,
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V U.S. NUCLEAR REGULATORY COMMISSION CaCC;E
{ NRC Form 189 (Part 3)
(10-93) W 134 NRCMD 11.7 MOC:FiCATiCN NUMBER l
- 14. SPENDING PLAN: *a:e w e- ;
l FY 1997
i!
NAME ;F LA6CRATCRV PERFOR'.%NCE PERICC !
eacM TO ll Oak Ridge . National Laboratory j 10194 I: 31 9- J
'l TITLE CF DROJECT To's esmaw m Of the DrOCCseo praed '
"* ' SK 3. 96*
Sequence Coding and Serch System g)e s sutmss,on ESTIMATED COST AND COMPLETION BY MONTH COST ELEMENTS OCTCBER NOVEMBER CECEMBER ,ANUARY FEBRUARY N%RCH I23 '23 84 93 93 C' RECT COST iSK)
INDIRECT COST isK) i42 I23 I23 04 93 93 TOTAL COST ($K)
)
PROJECT 63*h 6T's "0'. T2'6 75'o 77'k j COMPLETION (%)
m
)
ESTIMATED COST \ND COMPLETION BY MONTH I
COST ELEMENTS APRIL N%Y JUNE JULY AUGUST SEPTEMBER 0 09 DIRECT COST ($K)
~ - - -
INDIRECT COST isk) 8 0 TOTAL COST ($K)
?9 82 SD E 80
- 9I h 93*b hROJE o t IONi%)
' Cost esumates pertan to the October 1.1995, througn DecemDer 31.199'. penod NRC Form 199(6 956
-. - .c w ., a
e e
CBCCCE NRC Forrn 189 (Part 3) U.S. NUCLEAR REGULATORY COMMISSION (10-93) WI34 N RCMD 11.7 MOOiF. CATION NUMBER !l
' ' c"c*:* - h
- 14. SPENDING PLAN:
FY 1998 ,,
- I ,
NAME CF LABORATORY PERFORMANCE PERIOD l FROM TO f Oak RidgeN. atioral Laboraton ,
10194 12314~
l TITLE OF PROJECT Tota: estirratea ecsts I of the DroposeG project or j rnoaincaton at tne SK 3.~96*
Sequence Coding and Seuch S.sstem ome of croposal (
P 1 sub - son ESTIMATED COST AND LOMPLETION BY MONTH 1
COST ELEMENTS OCTOBER NOVEMBER 2CEMBER JANUARY FEBRUARY MARCH 0
DIRECT COST ISK)
INDIRECT COST f$K)
TOTAL COST ($K)
PROJECT 93g 9g.6 100's COMPLETION (%)
k 2.-
ESTIMATED COST AND COMPLETION BY MONTH l APRIL AAAY JUNE JULY AUGUST SEPTEMBER COST ELEMENTS DIRECT COST ($K)
INDIRECT COST ($K)
TOTAL COST (5K)
PROJECT COMPLETION I%)
- Cost estimates pertam to the October 1.1995, through December 31.1997, penod
.