ML20029D911

Forwards Request for Addl Info Needed by Staff in Order to Support Contract W/Science & Engineering Associates,Inc

ML20029D911
Person / Time
Issue date:	05/05/1994
From:	Scaletti D Office of Nuclear Reactor Regulation
To:	Snell V AECL TECHNOLOGIES
References
PROJECT-679A NUDOCS 9405120243
Download: ML20029D911 (5)

Text

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flay 5, 1994 Project No. 679 Dr. Victor G. Snell, Director Safety and Licensing AECL Technologies 9210 Corporate Boulevard Rockville, Maryland 205850

SUBJECT:

REQUEST FOR ADDITIONAL MATERIAL - CANDU 3 Enclosed is a request for additional information needed by the staff in order to support a contract with Science & Engineering Associates, Inc. The objectives of this contract are to provide the staff with insights into the applicability of NUREG-0933 issues to the CANDU 3 design and performance identifying potential safety problem areas that will need to be addressed during a future design certification review.

Also, apart from the information requested in the enclosure, please provide a copy of the AECLT Quality Assurance Manual that governs the CANDV 3 design development. This manual will provide the staff with an early understanding regarding your compliance with 10 CFR 50, Appendix B.

The information requested by this letter has been previously discussed with representatives of your staff.

If you have concerns regarding this request, please contact me at (301) 492-1104.

The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents, therefore OMB clearance is not required under P.L.96-511.

Sincerely, original signed by:

Dino C. Scaletti, Project Manager Advanced Reactors Project Directorate Division of Advanced Reactors 9405120243 940505 and Special Projects P

PROJ Office of Nuclear Reactor Regulation PDR

Enclosure:

1 Additional Information Request Of cc w/ enclosure:

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DISTRIBUTION:

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WASHINGTON, D.C. 20555-0001 May 5, 1994 Project No. 679 k

Dr. Victor G. Snell, Director Safety and Licensing AECL Technologies 9210 Corporate Boulevard j

Rockville, Maryland 205850 l

SUBJECT:

REQUEST FOR ADDITIONAL MATERIAL - C/.NDU 3 Enclosed is a request for additional information needed by the staff in order to support a contract with Science & Engineering Associates, Inc. The objectives of this contract are to provide the staff with insights into the applicability of NUREG-0933 issues to the CANDU 3 design and performance identifying potential safety problem areas that will need to be addressed during a future design certification review.

~

Also, apart from the information requested in the enclosure, please provide a copy of the AECLT Quality Assurance Manual that governs the CANDU 3 design development. This manual will provide the staff with an early understanding i

regarding your compliance with 10 CFR 50, Appendix B.

I The information requested by this letter has been previously discussed with l

representatives of your staff.

If you have concerns regarding this request, please contact me at (301) 492-1104, The reporting and/or recordkeeping requirements contained in this letter 2

affect fewer than ten respondents, therefore OMB clearance is not required under P.L.96-511.

j Sincerely,

[.

j l

Dino C. Scaletti, Project Manager Advanced Reactors Project Directorate Division of Advanced Reactors and Special Projects Office of Nuclear Reactor Regulation i

Enclosure:

Additional Information Request l

cc w/ enclosure:

See next page 1

4 CANDU Project No. 679 I

cc:

Louis N. Rib, Licensing Consultant AECL Technologies 9210 Corporate Boulevard, Suite 410 Rockville, Maryland 20850 l

A.M. Mortada Aly, Senior Project Officer l

Advanced Projects Licensing Group Studies and Codification Division Atomic Energy Control Board l

P.O. Box 1046, Station B 270 Albert Street Ottawa, Ontario, Canada KlP SS9 Project Director - CANDU-3 AECL CANDU l

2251 Speakman Drive Mississaugua, Ontario, Canada L5K 182 L. Hanning Muntzing l

Newman & Holtzinger, P.C.

i 1615 L Street, N.W., Suite 1000 Washington, D.C.

20036 Steve Goldberg, Budget Examiner Office of Management and Budget 725 17th Street, NW.

Washington, D.C.

20503 A.D, Hink Vice President / General Manager AECL Technologies 9210 Corporate Boulevard, Suite 410 Rockville, Maryland 20850

o Enclosure ADDITIONAL INFORMATION REQUESTED Canadian Regulatory Documents AECB,1987b, " Requirements for Reliability Analysis of Safety-Related Systems in Nuclear Reactors," Atomic Energy Control Board, Consultive Document C-98, Ottawa, Ontario, Canada, April 14.

Technoloay Transfer Reports Weaver, K.R., D.F. Torgerson, D.J. Wren, N. Garisto, and R.W. Holmes,"

Behavior of Iodine in the Heat Transport System and Containment and Application to loss-of-Coolant Accident Analysis for 600 MW(e) Reactors,"

TTR-41, June 1982.

Min, T.K. and T. Chan, " Hydrogen Mixing and Combustion in Reactor Vaults,"

TTR-91, Revision 1, July 1990.

M. A. Wright and M.S. Quraishi, " Analysis of the Consequences of an End Fitting Failure," AECL Report TTR-153, May 1985.

Quraishi, M.S., et al., " Analysis Methods, Assumptions and Data for Assessment of Enhanced Leakage from Containment Following a Postulated Accident,"

TTR-168, Volume 1, March 1986.

Quraisha, M.S., et al., " Assessment of Higher Leakage From Containment Following a Postulated Accident," TTR-168, Volume 2, September 1986.

Other AECL Documents Tamm, H., et al, " Overview of the Technical Basis for the Safety of CANDU Reactors," AECL Whiteshell Laboratories, AECL 9559, 1988.

" Power Pulse Break Study," Rev. O, AECL 74-03310-AR-001, October 1991.

C.E. Ells, W. Evans, "The Pressure Tubes in the CANDU Power Reactors," The Canadian Mining and Metallurgical Bulletin,1981 July (AECL-7344).

E.G. Price, " Fabrication, Inspection, and Properties of Current Production Pressure Tubes," AECL-CANDU Report TDV1 - 380, July 1982.

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Referenced Papers Dolbey, M.P, " CIGAR - An Automated Inspection System for CANDU Reactor Fuel Channels," ASME 8th International Conference on NDE in the Nuclear Industry, Orlando, Florida, November 1988.

Benton, D.J., "The SLAR System - An Overview," Proceedings of Canadian Nuclear Society 8th Annual Conference, St. John, NB, June 1987.

Kenchington, J.M., Ellis, P.J., and Meranda, D.G.,

"An Overview of the Development of Leak Detection Monitoring for Ontario Hydro Nuclear Stations,"

Proc. of the 8th Annual Conference, Canadian Nuclear Society, St. John, NB, 1987.

Tenankore, K.N., A.C. Vikis, G.M. Frescura, and J. Blyth, " Canadian Program on the Behavior of Reactor Containment Atmospheres During Postulated Accidents,"

The 2nd International Conference on Containment Design and Operation, Toronto, Ontario, October 14 through 17, 1990.

B.H. Mcdonald and B.N. Hanna, " Integrated Aerosol and Thermal-hydraulics Modeling for CANDU Safety Analysis," presented at the CNS/ANS Conference, April 18 through 20, 1990. Montreal, Canada.

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