ML20141H372

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Summary of 851119 Meeting W/Ge & DOE Re Design Requirements for Power Reactor Inherently Safe Module Liquid Metal Reactor Concept.Requirements Will Be Used to Develop Set of Principal Design Criteria for Plant
ML20141H372
Person / Time
Issue date: 01/06/1986
From: King T
Office of Nuclear Reactor Regulation
To: Speis T
Office of Nuclear Reactor Regulation
References
NUDOCS 8601130578
Download: ML20141H372 (3)


Text

s.

JAN O 61986 MEMORANDUM FOR:

Themis P. Speis, Director Division of Safety Review'and Oversight Office of Nuclear Reactor Regulation THRU:

Karl Kniel, Chief Safety Program Evaluation Branch Division of Safety Review and Oversight Office of Nuclear Reactor Regulation FROM:

Thomas L. King, Section Leader Safety Program Evaluation Branch Division of Safety Review and Oversight Office of Nuclear Reactor Regulation

SUBJECT:

SUMMARY

OF MEETING WITH THE GENERAL ELECTRIC COMPANY ON DESIGN REQUIREMENTS FOR THEIR LIQUID METAL REACTOR (LMR)

CONCEPT On November 19, 1985 representatives from the General Electric Company briefed us on the approach they are following in developing the design requirements for their Power Reactor Inherently Safe Module (PRISM) LMR concept. They also described how these requirements will be used.

The briefing is part of the-planned NRC-D0E interaction on LMRs.

Copies of the briefing objectives and list of attendees are enclosed. A set of viewgraphs used at the meeting is available for inspection at the section office.

The design requirements for PRISM will be used to develop a set of principle design criteria (PDCs) for the plant.

These PDCs must eventually be compared with existing PDCs (e.g., for the CRBR) but it is expected that there will be significant differences because of design innovations.

In addition, the licensing approach planned for PRISM by DOE and GE involves a one-step licens-ing supported by a safety test of a standardized design. This may require adjustments to the current regulations and criteria.

The NRC was not asked to review the design requirements formally at this time, hence the meeting was for information and informal feedback.

Highlights from the meeting are summarized below:

GE noted that their standard plant approach should not be interpreted to mean that a fixed configuration for the total plant would be offered but rather that a standard " safety related envelope" would constitute the standard plant.

Interfacing requirements between non-safety and safety grade plant features will be identified, defined and documented. These interfaces will be standardized and the designer will ask NRC to "cestify" the interface requirements; however, it is not GE's intent at this time to include the design of the non-safety grade balance of plant in the standard plant application. The staff indicated that this was an area of major concern and that early discussion and agreement on this aspect of the design was essential.

8601130578 860106 PDR TOPRP ENV9ENE C

PDR

d T. P. Speis * ' The general goals for the design include the use of inherent safety features, standardization, use of a full scale safety test, use of factory fabrication, minimizing safety related equipment and protection of public health and safety.

The staff suggested adding a goal related to addressing the Commission's severe accident policy and safety goal policy.

  • It is a goal of the design to satisfy the Protective Action Guidelines (PAGs) at the plant exclusion area boundary and, therefore, to eliminate

~the need for offsite evacuation.

The design requirements also include a goal of achieving one-step i

licensing at qualified sites after plant certification by NRC.

Questions were raised regarding some details of the design requirements.

The potentially significant one are:

- The requirements have no definition of single-failure, thus we would expect to use the definition currently applied to LWRs.

Requirements for in-service inspection (ISI) appear weak to the staff.

More would likely be required on the inherent safety features, such as periodic testing.

gristmalsigned by:

Thomas L. King, Section Leader Safety Program Evaluation Branch Division of Safety Review and Oversight Office of Nuclear Reactor Regulation

- DISTRIBUTIONg PDR Central File DSR0 Chron SPEB Rdg.

CAllen BSheron KKniel ZRoszteczy JSwift HHolz RColmar LSoffer RJohnson FEltawila DThatcher SShaukat PNorian EChelliah RCurtis, RES RAudette, RES MEl-Zeftawy, ACRS b

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0FFICIAL RECORD COPY g g g4 g

PRISM DESIGN REQUIREMENTS NOVEMBER 19, 1985 NAME ORGANIZATION TELEPHONE 1C. L. Allen NRR FTS 492-8345

.R. J. Audette RES/DAE FTS'427-4689 GeorgeLSherwood DOE /NE FTS 233-4162 Farouk Eltawila NRC FTS 492-9488 LThomas L. King NRC/NRR FTS 492-7347

-John H. Austin NRR/0CM FTS 634-3308-Neil W. Brown GE 408-738-7787 Khalid Shaukat NRR FTS 492-4216 R. Gluck GE-NST0 408-738-7537 R. Lange

. DOE /NE-53 FTS 233-5338-Richard E.-Johnson-NRR 301-492-4715 NRC/RES-301-427-4338 Charles Kelber s

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