ML20127F605

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Notification of 930210 Meeting W/Aecl & ORNL in Rockville,Md to Discuss Technical Issues Associated W/Candu 3 Reactor Design
ML20127F605
Person / Time
Issue date: 01/14/1993
From: Kennedy J
Office of Nuclear Reactor Regulation
To: Pierson R
Office of Nuclear Reactor Regulation
References
PROJECT-679A NUDOCS 9301200301
Download: ML20127F605 (4)


Text

January 14, 1993 Project No. 679 MEMORANDUM FOR:

Robert C. Pierson, Director Advanced Reactors Project Directorate Associate Directorate for Advanced Reactors and License Renewal, NRR FROM:

Janet L. Kennedy, Project Manager Advanced Reactors Project Directorate Associate Directorate for Advanced Reactors and License Renewal, NRR

SUBJECT:

FORTHCOMING MEETING WITH ATOMIC ENERGY OF CANADA, LTD.

TECHNOLOGIES AND OAK RIDGE NATIONAL LABORATORY (ORNL) ON THE CANADIAN DEUTERIUM URANIUM (CANDU) 3 REACTOR DESIGN DATE AND TIME:

Wednesday, february 10, 1993 9 a.m. - 5 p.m.

LOCATION:

U.S. Nuclear Regulatory Commission 5650 Nicholson Lane, Conference Rooms A and B Rockville, Maryland PURPOSE:

Discussion of various technical issues associated with the CANDU 3 reactor design.

(See attached agenda.)

PARTICIPANTS *:

NRC QML AECL/AECL TECH.

R. Pierson R. Meyer T. Wright P. Allen J. Kennedy E. Throm M. Line L. Rib, et al.

A. Szukiewicz J. Wolfgong, T.Cox, ei. al.

et al.

Original signed by:

Janet L Kennedy, Project Manager Advanced Reactors Project Directorate 9301200301 930114 Associate Directorate for Advanced Reactors P

PROJ PDR and License Renewal, NRR

Enclosure:

i,genda 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 Lederal Reaistez_28058, 06/28/78. However, portions of this meeting may be closed to the public to protect AECL Technologies proprietary information. Members of the public who wish to attend should contact J. Kennedy at.(301) 504-1140.

Distribution: See attached list PM:PDAR at SC:PDAR LA:ADAR g ' JKennedy:sa THCox d C-LLuther

/ //3/93 (1/N/93

///4/93 0FFICIAL RECORD COPY Document Name:

CANMTG02.10

Robert C. Pierson January 14, 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 K1P SS9 A.M. Mortada Aly, Senior Project Officer Ad,anced Projects Licensing Group Stadies and Codification Division Atomic Energy Control Board

'/.0, Box 1046, Station B 270 Albert Street Ottawa, Ontario, Canada KlP SS9 Project Director - CANDU-3 AECL CANDU 2251 Speakman Drive Mississaugua, Ontario, Canada L5K 182 L. Manning Huntzing 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 L

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

i 1

1 b

ENCLOSURE AGENDA FOR MEETING WITH AECL-CANDU, AECL TECHNOLOGIES AND OAK RIDGE NATIONAL LABORATORY TO DISCUSS CANDU 3 SYSTEMS RESEARCH Topic Presenter 1.

Introduction NRC 2.

CANDU 3 Systems Research Program at ORNL NRC/0RNL

- Purpose 3.

Review of CANDU 3 Event Sequence Diagrams ORNL/AECL 4.

Detailed Design Information AECL/AECLT a.

Crash Cooldown

- System Purpose and Function

- Initiation Signals b.

Emergency Core Cooling

- System Purpose, Operation and Function (including design requirements, e.g.,

operating pressure)

- Initiation Signals c.

Shutdown System No. I and No. 2

- Detailed Description of Trip Logic

- Single-Failure Proof

- Common Mode Failures d.

Group 1 and Group 2 Classification

- Safety Related vs. Non-Safety Related Systems

- Are Some Group 1 Systems Safety-Grade?

- What Does Safety Related Mean in Terms of Design and Operational Specifications for Systems so Designated?

e.

Significant Operator Actions 5.

Closing Remarks NRC l

l l

Q MEETING NOTICE - NRC/ ATOMIC ENERGY OF CANADA, LTD./0AK RIDGE NATIONAL LAB.

MEETING ON FEBRUARY 10, 1993 - DATED: January 14, 1993 DistributinD:

Central File NRC PDR PDAR R/F T. Murley 12/G/18 F. Miraglia 12/G/18 D. Crutchfield R. Pierson T. Cox E. Throm J. Kennedy Z. Rosztoczy NLS 169 A. Chaffee, EAB ll/A/l E. Jordan MNBB 3701 C. Rossi, CRIL 9/A/2 Receptionist, Nicholson Lane R. Meyer, RES NLS 013 A. Szukiewicz, RES NLS 013 ACRS (10)

P 315 OGC 15/B/18 OPA 2/G/5 Mail Room, PMAS 12/G/18 P. O' Dell, PTSB 12/E/4 L. Plisco 10/A/9 LLuther e

CANDU R/F PDAR Meeting File 150001 3)Fo3 I t-