ML20207R476
| ML20207R476 | |
| Person / Time | |
|---|---|
| Issue date: | 03/12/1987 |
| From: | Kniel K Office of Nuclear Reactor Regulation |
| To: | Sheron B, Speis T, Williams P NRC |
| References | |
| PROJECT-672, PROJECT-672A NUDOCS 8703170263 | |
| Download: ML20207R476 (5) | |
Text
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J MEMORANDUM FOR:
Distribution FROM:
Karl Kniel, Chief Safety Program Evaluation Branch Division of Safety Review and Oversight
SUBJECT:
MEETING WITH DOE TO REVIEW CHAPTER 4 0F MHTGR PRELIMINARY SAFETY INFORMATION DOCUMENT (PSID)
The subject meeting is the third of a series of meetings with DOE and its contractors to discuss NRC comments on the conceptual design for the modular HTGR.
The meeting will be held on March 18, 1987 in Room P-110 and on March 19, 1987 in Room P-422 and begin at 9:00 a.m. on both days.
An agenda is attached.
Chapter 4 deals with the reactor and is divided into the following sections:
4.1 Reactor System, 4.2 Reactor Core Subsystem, 4.3 Neutron Control Subsystem, and 4.4 Reactor Internals Subsystem.
Reviewers for Chapter 4, together with contractors from ORNL ans BNL, should plan to meet in Tom King's office at 1:00 p.m. on March 17, 1987 to discuss their planned comments on the forthcoming meeting.
If you have any questions please contact Pete Williams, the Project Manager (x29613).
Karl Kniel, Chief Safety Program Evaluation Branch Division of Safety Review and Oversight
Enclosure:
As stated
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i Agenda March 18, 1987 Meeting on MHTGR PSID Chapter 4 (Phillips Building; Room P-110) 9:00 a.m.
Opening Remarks - NRC, DOE, Others 9:15-10:45 a.m.
Reactor Core Subsystem I - Fuel and Materials Presentation by DOE / Contractors on fuel design, performance, and technology development plans.
Presentations to include discussions on the time effects on fuel (particularly EOC),
fuel quality assurance, means of prevention and consequences of fuel bicckage, effects of water ingress, dose evaluations, and the analytical supporting methods, assumptions, and the data base.
Presentation to include the role of FSV fuel both as a data base and technology development tool, dif-ferences in MHTGR and FSV fuel, failure thresholds and mechanisms.
In addition, design, performance and technology information to be presented on control materials, metal plenum elements, fuel and reflector graphite (including a discussion of the significance of fuel element graphite cracking in FSV).
11:00-12:00 p.m.
Comments by NRC and Discussion 12:00-1:00 p.m.
LUNCH 1:00-2:00 p.m.
Reactor Core Subsystem II - Nuclear Design and Reactivity Control Presentation by DOE / Contractor on nuclear design and reactivity control.
Status of GAT's nuclear design methods to be reviewed in context of available and planned benchmarking data, plans and approaches to meet SRP for PSAR/FSAR stages, uncertainties and accommodations of uncertainties in safety analyses in such areas as water ingress, rod worths, and temperature coefficient.
- Also, treatment of fuel cycle and LEU fuel, documentation of relevant data and verification of calculations using these data, role of industry standards, degree and effects of vessel fluence and power distribution uncertainties, GAT discussions with D.L. Moses.
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, i 2:00-3:00 p.m.
Comments by NRC and Discussion 3:00-4:00 p.m.
Neutron Control System Design and operation of control rods and drives, reserve shutdown systems, invessel and exvessel neutron detection equipment, neutron and gamma shields.
Also discussion of steady state and transient environmental protection, safety classifications, similarities and differences from FSV, technology development needs.
4:00-5:00 p.m.
Comments by NRC and Discussion 4
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March 19, 1987 Continued Meeting on PSID Chapter 4 9:00-10:00 a.m.
Reactor Internals Subsystem Presentations by DOE / Contractors on (1) Graphite Core Support Structure including considera-tions for both anticipated and accident conditions of potentials and consequences of thermal stress, seismic loads, combined thermal and seismic stresses, hot streaks, laminar flows.
Identification of data base and technology development needs.
(2) Upper Plenum Thermal Protection Structure including performance under anticipated and accident conditions with consideration for potentials and consequences for failure from flow induced vibrations, hot streaks, insulation inadequacies.
Identification of data base and technology needs.
(3) Other Metallic Structures which include the safety design and performance of the core lateral restraint, the metallic core support structure and hot duct assembly.
10: 00-11: 00 a.m.
Comments by NRC and Discussion 11:00-12: 00 p.m.
General Discussion and Discussion of Administrative Items
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