ML20058L839

Forwards GE Understanding of 930426 Telcon Between GE & NRC on SSAR Chapter 4 & Tier 1 for Review Re Acceptability. Verbal Would Be Appreciated by 930512

ML20058L839
Person / Time
Site:	05200001
Issue date:	05/05/1993
From:	Fox J GENERAL ELECTRIC CO.
To:	Poslusny C Office of Nuclear Reactor Regulation
References
NUDOCS 9305130022
Download: ML20058L839 (2)

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I May 5,1993 Docket No. STN 52 001 3

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Chet Poslusny, Senior Project Manager

-l Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal l

Office of the Nuclear Reactor Regulation l

i

Subject:

Submittal Supporting Accelerated ABWR Review Schedule - SSAR Chapter l

4 and Tier 1

Dear Chet:

t Attached is GE's understanding of the April 26,1993 telephone call between the NRC (Bill i

Russell) and GE (Joe Quirk, Tony James and Jim Klapproth) pertaining to SSAR Chapter 4 and Tier 1. I request that the NRC review this attachment as to its acceptability. Verbal response would be appreciated by May 12,1993.

i Please provide copies of this transmittal to Bill Russell, Bob Jones, Larry Phillips and Tom Boyce.

Sincerely, l

bey ack Fox Advanced Reactor Programs cc: _ Norman Fletcher (DOE) l~

Tony James (GE)

Jim Klapproth (GE)-

Joe Quirk (GE)

Caroline Smith (GE)

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JF91135 9305130022 930505 l.

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i ABWR CHAPTER 4 AND ITAAC i

The following information will be provided in Tier 1 and 2 for fuel, channels and control rods:

TIER 1:

Top level design description identifying key design features.

Top level design criteria. No ITA AC tables will be provided since these components are treated as consumables.

TIER 2: (SSAR Chapter 4)

Specific design criteria (similar to GESTAR Amendment 22 for fuel) -

currently provided as Appendix 4B for fuel and Appendix 4C for control rods.

i Description of the fuel design used for the reference core design with a ref-erence to the NRC SER which approved this design.

A detailed discus-sion of how the fuel design satisfies each of the design criteria will not be provided - general conformance with licensing requirements is demon-strated in the SSAR Chapter 15 analyses.

Discussion of the nuclear methods used to evaluate the reference core de-sign (e.g., ODYN-A, REDY-A).

1 Brief description of the control rod design.

NOTE: There will be no specific reference to GESTAR II or the Bundle Nuclear Design Report.

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