ML20062F795

Summary of 901026 & 26 Meetings W/Ge,Doe & Argonne on Advanced Liquid Metal Reactor Prism Design.Agenda & List of Attendees Also Encl

ML20062F795
Person / Time
Issue date:	11/15/1990
From:	Throm J NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:	Ader C NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
References
PROJECT-674A NUDOCS 9011280178
Download: ML20062F795 (14)

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MEHORANDUM FOR: Charles E. Ader, Chief, Advanced Reactors and Generic Issues 1

Branch, Division of Regulatory Applications, RES THRU:

Jerry N. Wilson, Section Leader, Advanced Reactors and.

Standard 1zation Section, Division of Regulatory Applications RES FROM:

E&:,rd O. Throm, Senior Reactor Systems Engineer, Advanced-Reactors and Generic Issues Branch, Division of Regulatory Applications RES

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SUMMARY

OF MEETINGS WITH GE, DOE, AND ANL ON THE ALMR PRISM DESIGN HELD IN ROCKVILLE, MD, ON OCTOBER 25 AND 26, 1990 NRC PROJECT 674 Three meetings were held with General Electric (GE) DOE, and Argonne National Laboratory (ANL) to discuss three review areas.related to the Advanced Liquid Metal Reactor (ALMR) Power Reactor Innovative Small Module (PRISM) design.

They are:

(1)

Seismic isolation.

(2)

Control room design, role of the operator, and multi-module control.

(3)

Metalfuelbehaviorduringunprotectedtransientoverpower(UTOP) events.

The agenda and attendees lists f or each of these three meetings are attached.

Because DOE considers the PRISM design to fall under the umbrella.of its Applied Technology provisbes, the viewgraphs used during these meetings are j

not included in this sumary.

Seismic Isolation L I i

The seismic isolation criteria and design were presented by GE. The isolators l-provide horizontal damping of ground motion. The reactor vessel and its internals, as well as equipment vaults which contain systems and-components important to safety, are located on the seismic island.

l l-A comprehensive research and development (R&D) program is supporting the design of the isolators and will be used in quantifying their performance.

The DOE seismic isolation program (SIP). goals are tc; (1)

Reduce overall seismic. hazard to facilities (2)

Simplify design, construction, and equipment qualification (3)

Reduce costs, and pQ12 8 901115 5

674A PDC

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2 (4)

Provide a technology base adequate for nuclear facilities.

With respect to PRISM, the SIP objectives also include assessment of issues of reliability, f ailure modes, and beyond design basis safety margins. The NRC staff has reviewed some of the SIP material and DOE and GE will be providing the staff with additional material.

The seismic isolation program is focused on the developnent of design tools (analytical model development), design guidelines, and reliable seismic isolation elements with well understood performance characteristics (isolation bearings properties and margin, materials development / environmental effects, etc).

The staff believes that the seismic isolation program will provide the needed inforraation regarding the design and performance of seismic isolators for the PRISM design.

The data will allow the NRC to make a final determination when the PRISH design certification is reviewed.

Control Room and Role of Operator The design goai of the control room is to optimize plant operation.

It is not safety grade. The remote shutdown facility (RSF) is a Seismic Category I, tornado hardened structure located about 40 feet from the control room building, and the distance traveled by the operator is estimated to be less than 120 feet.

The RSF is equipped with Class 1E electronics to perform safety functions. The control room has no Class 1E components.

The NRC discussed reasons why a Class 1E reactor trip system should be added to the control room design, however the staff also indicated that the remainder of the control room need not be fully safety grade. The rationale for the Class IE trip in the control room is based on uncertainties in the need for, and response time of, operator action to trip the reactor (s) for unforseen events. At this time the staff is unable to make a determination on whether prompt operator action will be required. One role of the operator is to serve as a backup to the safety systems.

In addition to the RSF, reactor shutdown can be accomplished from the equipment vaults on the seismic isolated nuclear island. This feature appears to meet the intent of GDC 19.

However, the habitability of the equipment vaults has not been addressed. GE will perform a habitability study of the equipment vaults.

The operator also provides a backup communications role during post-accident ronitoring if the primary data links (telephone and microwave) are lost. The RSF features appear to be adequate for this function. Our review for the ability to perform these functions from the equipment vaults is, at this time, inconclusive.

Multi-module control will be demonstrated in the prototype facility.

Metal Fuel Behavior The ternary metallic fuel (uranium, plutonium, and. zirconium--U-Pr-Zr) used in the PRISM design was discussed by ANL.

The discussions focused on the fuel conductivity and the characteristic of the unprotected transient overpower (UTOP) event.

3 NOV 15 1990 The key factor in understanding or evaluating the fuel is plutonium (Pu) redistribution with burnup. Some preliminary date-suggested significant I

redistribution of the Pu.

Newer data developed by ANL suggest that the-redistribution is not significant. ANL, through DOE, will provide the staff l

contractor, BNL, with the new data. Open literature will be provided.

The fuel conductivity and Pu relocation, as well as relocation of the U and Zr in the fuel matrix, can markealy alter the results (or at least the interpretation of the outcome)(U-Pr-Zr local concentrations) alters the expected from a transient or accident. The local composition of the fuel temperatures at which the fuel will change states and ultimately melt and fail.

Other issues concerning modeling of the fuel were discussed. GE will provide BNL with the justification for the peaking factors.

The fuel conductivity issue can be addressed through design changes. GE will identify potential design changes which could reduce the significance of the UTOP event if the fuel R&D program cannot resolve the. issue. Examples discussed include (a) reduced the rod stop settings to limit reactivity l

insertion, (b) lower the Pu content in the design fusi, and (c) lower the overall not thermal power level in the design core.

i t

Edward D. Throm, Senior Reactor Systems Engineer Advanced Reactors and Generic Issues Branch Division of Regulatory Applications Office of Nuclear Regulatory Research

Enclosures:

1.

Agenda & Attendee List for Seismic Isolation Mtg.

2.

Agenda & Attendee List for Control Room Design Mtg.

3.

Agenda & Attendee List for Metal Fuel Behavior Mtg.

cc: R. Hardy, GE C. Bigelow, DOE G. Gyorey, GE D. Petersen, ANL-N. Grossican, DOE G. Van Tuyle, BNL H. Alter, 30E OFor-distribution see next page. *Sg,EPREV Q. IRRENCE Offe: ARGIB:DRA ARGIB:DRA HSB:RES ?/ SSEi NI Name: *EThrom:rg *JWilson LBeltracj:hiRKesneally

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11/8/90 11/8/90 ll/g'/90 d /d/90 0FFICIAL RECORD COPY M

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Distribution:

PRISM

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ENCLOSURE 1 Agenda & Attendee List for Seismic Isolation Mtg.

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