ML20211H843

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Ack Participation of Calvert Cliffs Nuclear Engineering Dept in NRC Cooperative Research Project with Univ of Virginia. Copy of Relevant Portion of NRC Cooperative Agreement with Univ of Virginia Encl
ML20211H843
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 06/23/1999
From: Jocelyn Craig
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To: Cellars K
BALTIMORE GAS & ELECTRIC CO.
Shared Package
ML20211H825 List:
References
NUDOCS 9909020190
Download: ML20211H843 (38)


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'2 NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2066H001 I I

%***** June 23, 1999 )

l Mr. Kevin Cellars, Manager Nuclear Engineering Department Baltimore Gas and Electric Company l Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway, NEF-2 Lusby, Maryland 20657-4702

Dear Mr. Cellars:

The purpose of this letter is to acknowledge the participation of Calvert Cliffs Nuclear Engineering Department in the NRC's cooperative research project with the University of Virginia.

On May 11,1999, John Calvert and Joel Kramer of my staff, and Dr. Barry Johnson, Principal investigator for our cooperative research project at the University of Virginia, met with Bruce Geddes, Senior Engineer, I&C Engineering, and other members of your staff. The purpose of l the meeting was to discuss this cooperative research project and the potential for Baltimore Gas and Electric to participate. Enclosed is a copy of the relevant portion of the NRC Cooperative Agreement with the University of Virginia which will provide to you a better understanding of research issues.

This project is sponsored by the U.S. NRC Office of Nuclear Regulatory Research with an objective to develop the technical basis for guidance and acceptance criteria for risk-informed regulatory decision-making on digital system reliability. This effort is not a part of the NRC

! licensing or inspection program. Alex Dromerick and Guy Vissing of NRR's Division of .

Licensing Project Management, and Dave Solario NRC License Renewal Project Manager, are aware of this effort.

I

' We are encouraged by your staff's interest and willingness to participate with the University of Virginia in applying some of their research methods and simulation techniques to the Calvert  ;

Cliffs Digital Feedwater System. In this context, please be assured that should proprietary information be involved, we will deal with such information per processes and procedures  !

already in place.

9909020190 990727 PDR ADOCK 05000317 P PDR i

Kevin Cellars We look forward to your help and participation in this program. If you have any questions please contact me at (301) 415-5678 or John Calvert at (301) 415-6323.

Sincerely, John W. Craig, Director' /

Division of Engineering Technology Office of Nuclear Regulatory Research

Enclosure:

As stated cc: Dr. B. Johnson, U. of VA '

Dr. C. Smidts, U. Of MD

ATTACHMENT 2 List of Attendees Meeting on May 11,1999,10:00am to 12:00pm Calvert Cliffs Nuclear Power Plant, Nuclear Office Facility, Classroom 12

" Digital System Reliability Modeling" Name Title oraanization Phone Frank Arcella Systems Analyst BGE 410-495-4199 Jim Bennett Counsel BGE/ Legal 410-234-5607 Mark Draxton Process Manager BGE/ITAD 410-495-2379 Bruce Geddes l&C Engineer BGE 410-495-3712 Jeff Isakson Resident Site Mgr ABB CENP 410-495-6766 Bill Kemper Prin. Engr-l&C BGE 410-495-4000 Doug Lenker I&C Engr' BGE 410-495-4802 Donna Moeller Sr. Engineer BGE/ NRM 410-495-2061 Bill Nowicki l&C Engr BGE 410-495-2277 Paul Roller System Analyst BGE/ITAD 410-495-4343 Barry Thurston Project Manager BGE 410-495-6636 Mark Thomson System Analyst BGE/ITAD 410-495-6515 Barry Johnson Professor Univ. of Virginia 804-924-7623 John Calvert Sr. l&C Engr USNRC/RES 301-415'-6323 Joel Kramer Sr. Engr USNRC/RES 301-415-5891 ATTACHMENT 3 l

List of Attende.e.!g i Meeting on July 14,1999,10:00am to 2:00pm Calvert Cliffs Nuclear Power Plant, Nuclear Office Facility, Classroom 12

" Technical Interchange Meeting No.1 on Digital Feedwater Reliability Study"  ;

Name Title Oraanization Phone Frank Arcella Systems Analyst BGE 410-495-4199 Mark Draxton Process Mgr BGE/ITAD 410-495-2379 '

Bruce Mrowca Prin. Engr BGE/ Reliability 410-495-3989 Paul Roller System Analyst BGE/ITAD 410-495-4348 Barry Johnson Professor Univ. of Virginia 804 924-7623 Todd DeLong Senior Scientist Univ.of Virginia 804-982 2382 John Calvert Sr. I&C Engr USNRC/RES 301-415-6323 Terry Jackson l&C Engr USNRC/RES 301-415-6486 Eric Thornsbury Reliability Engr USNRC/RES 301-415-6216 u-_ _ _ - --- __- - __ _ _ - _ - _ - . _ _

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Reliability and Safety Modeling j Presented to:

Nuclear Regulatory Commission Advisory Council on Reactor Safety Presented by:

Barry W. Johnson Professor and Co-Director Center for Safety-Critical Systems University of Virginia May 3-4,1999

2. ~i Universityof virgin 6e Center for Safety 4rttical systems Outline introduction a University of Virginia s Center for Safety-Critical Systems e Embedded Real-Time Safety-Critical Digital Systems Research Objectives Digital System Reliability and Safety Assessment s Reliability and Safety Assessment Methodology a Reliability and Safety Modeling and Simulation Techniques a Tools to Support the Assessment Methodology a Application of the Assessment Methodology Conclusions Discussion

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! Center for Safety-Critical Systems

History Research in safety-critical systems has been on-going for the past 15 l years within the University of Virginia s Center for Semicustom integrated l Systems (CSIS) a CSIS founded in 1984 m CSIS established as a state of Virginia Center of Excellence in 1986 Safety-critical systems research program has designed, implemented, and tested multiple experimental prototypes of safety-critical systems l l

s Electric wheelchair controller (three separate prototypes) e Automatic train protection system (two separate prototypes) e Magnetic bearing controller (four separate prototypes)

Funded research activities at University of Virginia have grown to more than $1 million per year l

Center for Safety-Critical Systems was established in July 1998 47444 Endr 1 l

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Univoretty or virgin 6e l center far setetycritices systems Center for Safety-Critical Systems Participants Three departments and six faculty infolved at the University of Virginia e Department of Electrical Engineering a Department of Computer Science o Department of Systems Engineering Research collaborations with five other universities (five faculty members) e University of Maryland - College Park e College of William and Mary a Technical University of Braunschweig (Germany) i e Carnegie Mellon University a Penn State University

! Founding membership of the center advisory board u Nuclear Regulatory Commission

! e Federal Railroad Administration l s New York City Transit Authority l s Federal Transit Administration l s National Transportation Safety Board I a American Association of Railroads I e Inter-Modal Transportation Institute

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univernay of virginia center for sesetyr.,nimi sresems Center for Safety-Critical Systems Research Sponsors 1998-1999 Projects a Nuclear Regulatory Commission a Federal Railroad Administration m National Science Foundation m NASA Langley Research Center m New York City Transit Authority a Air Force Research Laboratory eDepartment of Navy Advanced Amphibious Assault Vehicle Program a Virginia s Center for innovative Technology Pending New Projects a Volpe National Transportation Research Center a Federal Transit Administration a Boeing a New York City Transit Authority e Illinois Department of Transportation univoreny of virginia Center for Safety <,rttical $yeesms Center for Safety-Critical Systems Research Areas Reliability and safety assessment methodologies and processes Reliability and safety modeling using analytical methods Analytical model solution techniques Human factors and human reliability Modeling and simulation of integrated hardware / software systems Distributed computing for complex model solution and simulation Fault modeling and fault simulation for hardware / software systems Statistical methods for reliability and safety estimation Computer-aided tools for reliability and safety modeling l Computer-aided tools for fault simulation of hardware / software systems Architectures for safety critical systems Safety-critical systems using commercial off the shelf (COTS) components ,

Experimental prototyping and testing of safety-critical systems  !

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university of Virginia Center for Safety 4rttical Systems Center for Safety-Critical Systems Research Facilities integrated Circuits Laboratory (ICL) e CAD tools for integrated circuit design eintegrated circuit test facility s integrated circuit fabrication through the NSF MOSIS program  !

m High performance workstations for modeling and simulation Software Development Laboratory (SDL) l e Tools for embedded software development l

e Processor emulation capability j

e Embedded software test capabilities l Systems integration Laboratory (SIL) l m Printed circuit board design capability e Printed circuit board assembly and test facility (surface mount)

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l m Hardware / software integration and test facility i

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i h Embedded System Structure on ore,ty Center for Safety 4rttical Systems i

l Feedback from Equipment / Commands to Equipment /

Commands from Humans l Equipment l , Information to Humans j l Human l

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I unswere, c.n,ortty or - virginie s-Trends in Embedded Systems Replacing analog circuitry, mechanical devices, and electro-mechanical l relays with digital (hardware and software) systems 1

( a Nuclear reactor protection systems l m Railway control systems e Aircraft flight control computers a lmplanted medical devices Transitioning from total human control to human-assisted control or totally automated control a Driverless trains a Positive train control and positive train separation a Fly by-wire flight control e Automatic shutdown systems .

i increasing use of commercial off the shelf components

! e Processors a Real-time operating systems  ;

I e Communications networks (data highways) increasing hardware / software and application complexity 47990 Ehe il l

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Research Objectives Develop a reliability and safety assessment methodology for digital systems a Consider the integrated hardware / software system a Allow for the inclusion of commercial off the shelf (COTS) hardware and software components l Develop modeling and simulation techniques that support the assessment j methodology l s Support the estimation of quantitative metrics l e Support the evaluation of qualitative attributes l Develop a set of tools that supports the assessment methodology l s Use COTS software tools where feasible l m Create new tools where needed Demonstrate the resulting approach and tools on real examples a Nuclear reactor protection systems (Virginia Power) l a Railway syctems (CSX and Federal Railroad Administration) i e Aircraft flight control (NASA and Boeing) 40990 she u l

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l Metrics l l 1r j Markov, Foult , Axiomatic , Estimated Parameters Tree Petri met,etc. , Models 1r Coverage, Failure 1 , Critical Rates, Latencies, etc. ' Parameters Parameter Estimation i t iP t t i Analytical Expert Worst Case Physical Simulation q l ,_ Models Opinion Estimates Models Models j l

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O LWwomity of Wginia Center for selety<,rtlical systems UVA Tools Developed to Support the Reliability and Safety Assessment Process ADEPT (Advanced Design Environment Prototype Tod) e Developed by UVA under a DARPA research project e Supports data fiow as a primary modeling abstraction a Supports hardware / software modeling a Supports all levels of the hierarchical modeling methodology a Based on VHDL as a modeling and simulation language a Based on Petri nets, Markov models, and fault trees as analytica! ,

models a Supports fault simulation at all levels of modeling abstraction ROBUST e Developed by UVA under an Air Force Research Lab research project e Supports hierarchical fault modeling and simulation a Supports hardware / software modeling e Automates analysis of fault simulation results a Based on VHDL as a modeling and simulation language e Supports distributed simulation of modeis 2.eu

-s h Examples of UVA Modeling Research ur oreit. we center for seesty4:ritient systems Jehesse,3. sad Ayler,J, Benehmey and Esfety Assytds

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Sadeh, D.Jehesse, B.and Presas til,J spumme Dependatasy Models Mosfels sees see at 8, A 1986, 4-m, Data mw Data Flow Saheen, M.Jehasse, B.and Ayler, J. Sampessumentes headst af as Operator lastmet6on leserveuse set Arcensureure LWeg VHDL , IEEE Dratre and Tes, Neis Esecuties (Canyumrs, vel le, Na 3, Espt 19P3, pp 43 94- Mastels DeLees.T.Juhassen, B.and PrussesIX.J. A Fandt laisrese Models Gate [4 vel Terhaique for VHDL Behowleraktmal Madmis , JEEE Dralps med Test Maggelg p  ;

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canor ter r - ces systems Process Applied this process to a real-time, safety-critical digital system a System in the field for more than a decade at 150 locations a System contains more than 30,000 lines of assembly code a 250 millisecond response time requirement a System was designed as an event-driven system l J

Simplex system with extensive software-based diagnostics a 80% of software written for diagnostic purposes Fail-safe application (shut down is considered safe)

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Safety requirements were qualitative and quantitative Quantitative a Mean Time Between Hazardous Events (MTBHE)

+ 105 years for the complete system e 107 years for any single processor unit a Fault detection time Total time of 250 ms in certain a Reconfiguration time cases and 500 ms in other cases aTime to perform a safe shutdown Qualitative a Correct operation of hardware / software system in the presence of prescribed faulty conditions a Correct functional behavior under fault-free conditions

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university of virginia center for satetycensesi syenema Structure of the Overall System Communications Bus ,

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Analogy Saber VHDL Mentor Graphics ADEI'T Vantage

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Smith, D., Johnson, B., and Profet2,III, J., System Dependability Evaluation ~

Using a Fault List Generation Algorithm , IEEE Transactions on Conputers, Vol. 45, No. 8, Aug.1996, pp. 974-979.

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Ovunasvered fauli Endth,D.,Jabiumn,S Andrission,N.and Profeta,(H,J. A Variance Redurton Tec' nique a Lising Fault Espans6an for Iadt Coverage Easniattom , lEEE Tressermens es ReAeMuy, Vol. 46, No. 3, Sept 1997, pp. 366 374.

Univoralty of Virginie comer tar Seestym Systems Safety Assessment Results Discovered 3 latent design faults that were safety significant Demonstrated safety-critical operation of the system Results used at proof of safety for a public utility commission identified design techniques to ensure meeting safety requirements and to ease the process of safety assessment 3 .-

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l u m nyorvi,sim cann tw semyomeni sy Conclusions (Lessons Learned)

Evaluate the integrated hardware / software system Develop a higher level of modeling abstraction Create a new theory for integrated hardware and software modeling Develop a new theory to support integrated modeling of design and operational faults Develop techniques to prove the correctness of software algorithms Provide integrated modeling tools and environments Develop techniques to establish confidence levels for safety estimates Exploit knowledge of the system in the assessment process Develop design principles which make assessment easier Create techriques for reliability modeling of hardware / software systems and integration of results into the PRA Develop techniques to handle hardware / software common mode faults Provide more experimental research to provide proof of the concept am ~ . ,

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ATTACHMENT 6 l

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'?' NRC/UVA Projcct l 5 DFW Documentation inventory NORMS ID Rev. Desenption Proprietary?

1 SYSD-045-0001 0000 FW System Description No (2; SR0032 0004 DFW System Requirements Document A

  1. 32 SD0020 0003 DFW SDD Lyes)

(4' HZ0009 0002 DFW Hazards Analysis Yeg 5 SR0012 0001 MFV Controller SRS No l 6 SR0013 0001 BFV Controller SRS No l 7 SR0014 0002 SGFP Controller SRS No -

8 Sf0015 0003 PDI Attemate Controller SRS No l

9 SD0008 0004 DFW Controllers SDD No 10 64302 0003 Unit 1 FW & Cond. Simplified Dwg. No 11 64305 0003 Unit 1 RCS Simplified Dwg. No 12 60920SH0019 0012 SG11 Loop Diagram No 13 60920SH0019A 0005 SG11 Loop Diagram - Analog No 14 60920Sh0019B {

0002 SG11 Loop Diagram - Digital No 15 60920SH00190 0006 SG11 Loop Diagram - Neutron Flux No 16 60920SH0020 0012 SG12 Loop Diagram No 17 60920SH0020A 0004 SG12 Loop Diagram- Analog No 18 60920SH0020B 0002 SG12 Loop Diagram - Digital No 19 60920SH0020C 0005 SG12 Loop Diagram - Neutron Flux No 20 N/A N/A F&P instruction Bulletin No 21 N/A N/A Azonix-7000 User's Manual No 22_ SWO201 07.00 Unit 1 DFW Controller Software No )

43 SWO274 02.00 Unit 1 DFW Source Code /fes) )

$4 SWO275 02.00 Unit 1 DFW Executable %ts/ '

25 SWO276 02.00 Unit 1 DFW Setpoints No 26 SWO277 00.00 Unit 1 DFW Configuration File No i

5 0

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I Distribution:

cooies w/o atts*

  • J. Craig
  • A.Thadani
  • J. Calvo G. Marino J. Mauck j J.C. Stewart q CC SRI J.S. Stewart )
  • G. Vissing, D. Solorio
  • M. Riggs M. Federline
  • J. Strosnider
  • M Evans J. Kramer ,

A. Dromerick l E. Thomsbury T. Jackson

  • T. King )

N.Siu '

'M. Cunningham R. Brill C. Antonescu

  • J. Rosenthal Public Document Room 50-317,50-318 BCC w/atts I i

Dr. Barry Johnson, UVA Dr. Carol Smidts, UMD ,

L