ML20056G111
| ML20056G111 | |
| Person / Time | |
|---|---|
| Issue date: | 08/20/1993 |
| From: | Scaletti D Office of Nuclear Reactor Regulation |
| To: | Miraglia F, Murley T, Russell W NRC |
| References | |
| PROJECT-679A NUDOCS 9309020067 | |
| Download: ML20056G111 (5) | |
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'o UNITED STATES l )"gg[,,n NUCLEAR REGULATORY COMMISSION U,
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August 20, 1993 Project No. 679 t
MEMORANDUM FOR:
T. Murley G. Lainas C. Rossi F. Miraglia J. Roe R. Zimmerman W. Russell J. Zwolinski B. Boger J. Partlow M. Virgilio C. Thomas D. Crutchfield B. Grirras F. Congel W. Travers J. Richardson E. Butcher F. Gillespie B. Liaw W. Bateman, EDO S. Varga A. Thadani A. Vietti-Cook J. Calvo G. Holahan Operations Center E. Merschoff, RII
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Edward D. Throm, Acting Director Advanced Reactors Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation FROM:
Dino C. Scaletti, Sr. Project Manager Advanced Reactors Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation
SUBJECT:
DAILY HIGHLIGHT - FORTHCOMING MEETING WITH WITH AECL TECHNOLOGIES (AECLT)
DATE & TIME:
August 25, 1993 9 am - 5 pm LOCATION:
U.S. Nuclear Regulatory Commission One White Flint North, Room 4/8/13 Rockville, Maryland PURPOSE:
Discuss the results of staff calculations of the response of CANDU 3 to a large break LOCA without scram. Also, discussion of staff's data base assessment (see agenda).
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Multiple Addressees August. 20, 1993 PARTICIPANTS *:
NRC AECLT AECH E. Throm V. Snell A.M. Mortada Aly R. Meyer, RES L. Rib, et al.
D. Carlson, RES D. Ebert, RES D. Scaletti, NRR, et al.
Original signed by:
Dino C. Scaletti, Sr. Project Manager Advanced Reactors Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation
Enclosure:
Agenda cc w/ enclosure:
See next page
- Meetings between NRC technical staff and applicants or licensees are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to "Open Meeting Statement of NRC Staff Policy," 43 Federal Reaister 28058,06/28/78. However, portions of this meeting may be closed to the public to protect AECL Technologies proprietary l
information. Members of the public who wish to attend should contact D. Scaletti at (301) 504-1104.
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Multiple Addressees August 20, 1993 CANDU Project No. 679 cc: Louis N. Rib, Licensing Consultant AECL Technologies 9210 Corporate Boulevard, Suite 410 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 559 A.M. Mortada Aly, Senior Project Officer Advanced Projects Licensing Group i
Studies and' Codification Division Atomic Energy Control Board P.O. Box 1046, Station B 5
270 Albert Street Ottawa, Ontario, Canada KlP SS9 Project Director - CANDU-3 AECL CANDU 2251 Speakman Drive Mississaugua, Ontario, Canada L5K IB2 l
L. Manning Muntzing Newman & Holtzinger, P.C.
1615 L Street, N.W., Suite 1000 Washington, DC 20036 Steve Goldberg, Budget Examiner Office of Management and Budget 725 17th Street, NW.
Washington, DC 20503 Mr. A.D. Hink Vice President / General Manager AECL Technologies 9210 Corporate Boulevard, Suite 410 Rockville, Maryland 20850
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Eaclosure MEETING AGENDA j
CANDU 3 i
AUGUST 25, 1993 l
i I
9 am - Thermal-Hydraulic-Neutronic Calculations (David Ebert & INEL)
I The staff used the Canadian code suite that includes CATHENA and POWDERPUFS, to do calculations of the LOCA without scram. A number of J
parametric variations were made in the calculations as listed below 1.
Vary D 0 Purity 93-99.7%
3 2.
Vary Critical heat flux 3.
Vary Heat transfer coefficient by 20%
4.
Break all four inlet headers S.
Start at 70% power rather than 100%
6.
Delay scram by one second after a LOCA.
l 7.
No LOCA but rather an inadvertent rod withdrawal r
12 noon -
Lunch I pm - Comparison of Reactivity Transients in CANDU with Others (David Ebert) f Compare the CANDU response to reactivity transients with the responses previously calculated for other reactor designs as follows:
1.
PWR rod ejection.
2.
BWR turbine trip without bypass.
3.
PRISM core disruptive accident.
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4.
TRIGA super prompt critical pulse.
l l
2 pm - Analysis of Coolant Void Reactivity in CANDU 3 (Don Carlson)
.1 (Three sets of neutronic codes are available. One is the Canadian i
POWDERPUFS code (PPV), one is a combination of COMBINE (INEL) and ANISN (ORNL), and one is the Monte Carlo code MCNP (LANL)).
1.
Compare PPV and COMBINE /ANISN calculations of infinite lattice void reactivity for the cases of:
a) fresh fuel versus average-burnup fuel, b) nominal coolant purity versus below-nominal purity, c) high coolant temperature versus low coolant temperature, and d) high fuel temperature versus low fuel temperature.
2.
Discuss COMBINE /ANISN calculations to examine the void reactivity reductions that result from changing the fuel enrichment, coolant composition, and lattice spacing.
3.
Results of calculations for selected case use of the continuous-energy Monte Carlo code (MCNP)
MEETING AGENDA CANDU 3 (Continued) 3 pm - Data Base Assessment (INEL, ORNL, SNL)
- 1. Reactor Physics (INEL)
- 2. Thermal-hydraulics (INEL)
- 3. Fuels
- i. A00s, DBAs (INEL)
- 11. Severe Accidents
- a. Core material (0RNL)
B. Source terms (SNL) 5 pm - Adjourn m
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