ML20058C709
| ML20058C709 | |
| Person / Time | |
|---|---|
| Issue date: | 11/22/1993 |
| From: | Scaletti D Office of Nuclear Reactor Regulation |
| To: | Hink A AECL TECHNOLOGIES |
| References | |
| PROJECT-679A NUDOCS 9312020545 | |
| Download: ML20058C709 (5) | |
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November 22, 1993 Project No. 679 Mr. A.D. Hink Vice President / General Manager AECL Technologies 9210 Corporate Boulevard, Suite 410 Rockville, Maryland 20850
Dear Mr. Hink:
SUBJECT:
REQUEST FOR ADDITIONAL MATERIALS 4
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 CANDU 3 containment system design and performance identifying potential safety problem areas that will need to be addressed during a future design certification review.
The staff believes that this effort is consistent with the containment performance topic proposed for early review in your August 3, 1993, letter to the NRC (
Subject:
Continued CANDU 3 Preapplication Review).
l The information in the enclosure was previously discussed with representatives of your staff at a meeting on October 28, 1993.
If you have concerns regarding this request, please contact me at (301) 504-1104.
l The reporting and/or recordkeeping requirements contained in this letter affect fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, Original signed by:
Dino C. Scaletti, Sr. Project Manager 4
Advanced Reactors Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation
Enclosure:
Request for Material cc w/ enclosure:
See next page Distribution:
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Mr. A.D. Hink November 22, 1993 CANDU Project No. 679 cc:
Louis N. Rib, Licensing Consultant AECL Technologies 9210 Corporate Boulevard, Suite 410
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Rockville, Maryland 20850 Bernie Ewing, Manager Studies and Codification Division Atomic Energy Control Board P.O. Box 1046, Station B 270 Albert Street Ottawa, Ontario, Canada KIP SS9 A.M. Mortada Aly, Senior Project Officer l
Advanced Projects Licensing Group Studies and Codification Division 3
Atomic Energy Control Board
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P.0 Box 1046, Station B
?70 Albert Street Ottawa, Ontario, Canada KlP SS9 Project Director - CANDU-3 I
AECL CANDU 2251 Speakman Drive Mississaugua, Ontario, Canada L5K IB2 L. Manning Muntzing Newman & Holtzinger, P.C.
ing C ib36 Steve Goldberg, Budget Examiner Office of Management and Budget 725 17th Street, NW.
Washington, DC 20503
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Enclosure l.0 ADDITIONAL INFORMATION REQUEST
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This request for additional information asks for a number of CANDU 3 i
referenced reports whose titles imply that they contain information relevant to the containment review.
Since this list of reports is not all-inclusive, we are also requesting more detailed, more current, or more applicable information, where available.
l.1 Prevailina Dfsion:
Provide revisions and updates to the 1989 Technical Description and the 1989 Conceptual Safety report, if they exist. The CSR mentioned a "CANDU 3 Standard Plant Safety Report" and " Safety Analysis Basis Reports" which were not yet completed.
Provide any of these reports that might now be available.
1.2 [pncrete Conlainment:
Provide any additional information relating to specifics of the containment design and acceptance criteria that can be 1
reviewed at this time.
For example, additional drawings showing orthogonal cross sections, elevations, internal structures, and details, such as the liner, sump, etc.
i 1.3 Containment Source Terms and Containment Responsgi In addition to possible revised or expanded safety analysis reports, provide the following referenced reports where applicable to the CANDU 3 design development.
- " Accident Analysis for 17% Uprated CANDU 600," AECL CANDU Operations, 1986.
- M. S. Quraishi, "CANDU 300 Containment Node Link Models," AR 03500-002.
- M. A. Cormier, " Containment Node Link Model for the CANDU 3 Design,"
AR-74-68400-002.
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- J. M. Hopwood, R. S. Porter, S. Pang, B. A. Shalaby, S. D. Grant, E. Kohn, A. Lai, V. K. Molindra, "Large LOCA Power Transient Assessment for CANDU 3,"
AR-74-03500-016, 1989 January, i
- S. D. Grant, V. I. Nath, "A Study of Pressure Tube Heat-Up following Postulated Large Breaks in an Inlet Header," AR-74-03500- 022, 1989 January.
- M. A. Wright and M. S. Quraishi, " Analysis of the Consequences of an End fitting failure," AECL Report TTR-153, 1985 May, 1.4 Radionuclide Source Terms and Release Rates:
Provide CANDU 3 specific radionuclide source term and release analysis reports, if available and the following reports if applicable to the CANDU 3 design develop;nent.
- G.1. Hadaller, G. H. Archinoff, and E. Kohn, "CANDU Fuel Bundle Benavior During Degraded Cooling Conditions," 4th Annual Conference of the Canadian Nuclear Society, Montreal,1983 June.
- E. Kohn, G. I. Hadaller, R. M. Sawala, G. I. Archinoff and S. L. Wadsworth, "CANDU fuel Deformation During Degraded Cooling - Experimental Results,"
j Canadian Nuclear Society Conference, 1985 June.
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1.5 Desian Basis and Severe Accidents:
Provide reports addressing CANDU 3 severe accident analysis, if available, including probabilistic analysis of beyond design basis events.
1.6 Performance of Unioue Features: We request the following referenced reports if applicable to the CANDU 3 design development.
- AECL, " Unique Aspects of the CANDU 3 Design," Atomic Energy of Canada, limited, June 1989.
- S. D. Grant and J. M. Hopwood, "The Effect of Fuel Heat Transfer on Early Void Production Following a large Pipe Break in CANDU Reactors," Canadian i
Nuclear Society Simulation Symposium, Winnipeg, Manitoba,1988 April.
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- P. G. Gulshani, " Prediction of Pressure Tube Integrity for Large Loss-of-Coolant Accident in CANDU," American Nuclear Society,1987 Winter Meeting, Los Angeles, CA, 1987 November 15-19.
- V.1. Nath and Kohn, "High Temperature Oxidation of CANDU Fuel During a LOCA," Proceedings of the Fifth International Meeting on Thermal Nuclear Reactor Safety, Karlsruhe, 9-13 September,1984, Kraftwerk Union Report KFK 388011, 1984 December.
1.7 Reaulatory and Standards Documents: We request the following reports.
- AECB, " Requirements for the Safety Analysis of CANDU Nuclear Power Plants,"
Atomic Energy Control Board, Consultative Document C-6, Ottawa, Ontario, Canada, 1980 June.
- The latest version of the folicwing Canadian Standards where applicable to the CANDU 3 design.
CAN3-A23.3-M84,
" Design of Concrete Structures for Buildings" CAN3-N287.1-H82, " General Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants" CAN3-N287.2-M91, " Material Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants" CAN3-N287.3-M82, " Design Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants" CAN3-N287.4-M92. " Construction, Fabrication, and Installation Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants" CAN3-N287.5-M81, " Testing and Examination Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants" ;
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CAN3-N287.6-M80, " Pre-Operational Proof and Leakage Rate Testing Requirements for Concrete Containment Structures for CANDU Nuclear Power
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Plants" j
CAN3-N287.7-M80, "In-Service Examination and Testing Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants" CAN3-N289.1-80,
" General Requirements for Seismic Qualification of CANDU Nuclear Power Plants" CAN3-N289.2-M81, " Ground Motion Determination for Seismic Qualification of CANDU Nuclear Power Plants" CAN3-N289.3-M81, " Design Procedures for Seismic Qualification for CANDU Nuclear Power Plants" CAN3-N289.4-H86, " Testing Procedures for Seismic Qualification of CANDU Nuclear Power Plants" 4
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