ML20094P367

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Forwards Tier 1 Design Certification for GE Advanced BWR Design - Stage 2 Submittal, Including Descriptions & Proposed Insps,Tests,Analyses & Acceptance Criteria (ITAAC) for 40 Advanced BWR Sys.Lists Info Not Covered by Rept
ML20094P367
Person / Time
Site: 05200001
Issue date: 04/06/1992
From: Marriott P
GENERAL ELECTRIC CO.
To: Pierson R
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML20094P370 List:
References
MFN-073-092, MFN-73-92, SLK-9244, NUDOCS 9204080069
Download: ML20094P367 (2)


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April 6, 1992 MFN No. 073 92 Docket No. STN 52 001 SLK-9244 Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention:

Robert C. Pierson, Director Standardization and Non Power Reactor Project Directorate

Subject:

Tier 1 Design Certification Material for the GE ABVR Design.

Stage 2 Submittal.

Enclosed are thirty-four (34) copies of the Stage 2 GE ABVR Tier 1 Design Certification material.

The Stage 2 material includes Tier 1 desi n 5

descriptions and proposed inspections, tests, analyses and acceptance criteria (ITAAC) for forty (40) ABWR systems. Also included is Tier 1 material covering selected generic issues as well as entries defining the technical interfaces between the certified design and site specific design features.

This submittal represents fulfillment of the GE commitment to submit Stage 2 Tier 1 material by 3/31/92.

The enclosed material does not include the following information:

1.

ITAAC-related changes resulting from disposition of the Interface items that were discussed during the 3/25-26/92 GE/NRC meetings in San Jose.

When there is GE/NRC consensus on these dispositions, the necessary ITAAC modifications will be made and submitted to NRC.

2.

Modification of the generic piping material to reflect the larger issues raised by the 3/23/92 through 3/26/92 NRC audit of ABWR piping.

The enclosed piping material has been modified in response to the more limited NRC comments on the current scope of the proposed ITAAC. When there is GE/NRC consensus on the larger issues, the Tier 1 piping material vill be modified and submitted to NRC.

3.

Tier 1 material for the Human Factors Engineering (HFE)/ Main Control Room design process.

This issue is currently being actively reviewed by CE and NRC and by mutual agreement is not addressed in the enclosed Stage 2 submittal.

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Document Control Desk April 6, 1992 U. S. Nuclear Regulatory Commission MFN No. 073 92 Washington, D. C. 20555 Docket NO. STN 52-001 SIX 9244 4.

The Reactor Building Tier 1 material and the arrangement drawings supporting the radiation protection entries. We are having production difficulties with this material and it will be submitted separately as soon as it becomes available.

CE views the enclosed material as Draft in the sense that we fully anticipate technical interactions with the staff and modificatiens of the enclosed material similar to the process which occurred on the pilot example material submitted earlier.

Based on comments at the 3/25/92 through 3/26/92 CE/NRC meetings in San Jose, it is our understanding that within approximately two weeks the NRC staff will inform CE of the expected schedule for the first round of NRC comments on the enclosed Stage 2 material.

Sincerely, 10f/

\\wo P. W. Marriott, Manager Regulatory and Analysis Services M/C 444, (408) 925-6948 Enclosure cc: F. A. Ross - DOE N. D. Fletcher DOE C. Poslusny, Jr. - NRC R. C. Berglund - GE J. F, Quirk - CE

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