ML19329B047

Forwards Structural Engineering Branch Notes on Preliminary Review of Fsar.Info About 97% Complete & Adequate to Perform Evaluation

ML19329B047
Person / Time
Site:	Davis Besse
Issue date:	01/02/1973
From:	Maccary R US ATOMIC ENERGY COMMISSION (AEC)
To:	Deyoung R US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8001300646
Download: ML19329B047 (4)

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uccket File 50-346 L:TR SEB RF M

2 $73 G. Arndt I

Docket No. 50-346 R. C. DeYoung, Assistant Director for Pressurized Water Reactors Directorate of Licensing i

l TOLEDO EDISO:I CO!!PANY - DAVIS-BESSE liUCLEAR POWER STATIOil -

PRELIMINARY REVIEW OF FSAR 4

Plant llame:

Davis-Eesse Nuclear Power Station Licensing Stage:

Preliminary Review of FSAR Docket Number:

50-346 Responsible Branch and Project Manager:

PWR 14, H. Faulkner Requested Completion Date:

January 3, 1973 Ispplicant's Responsa Cate Necessary for Completion of i

Next Action Planned on Project:

Unknown Description of Response:

Preliminary Revi3w Review Status:

Completed The preliminary FSAR submitted by the applicant has been reviewed by the Structural Engineering Branen to evaluate its acceptability.

The enclosure, Preliminary Review Notes, presents details on the review of the applicant's praliminary FSAR.

The overall assessment indicates that in the reviewed sec-tions of assigned responsibility about 3% of the information currently required by the Standard Format and Content of Safety Analysis Report 3 is considered missing.

However, tha information contained in the FSAR is adequate for us to perform an evaluation.

The section numbering and scope of information in each section conforms to the SAR format.

Sixteen (16) man hours were required for the review.

i R.

R. Maccary, Assistant Director for Engineering Directorate of Licensing

Enclosure:

Preliminary Review Notes f

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t JAN 2 1973 THE TOLEDO EDISON COMPANY i

DAVIS-BESSE Nyrm POWER STATION Docket No. 50-346 Preliminary Review Notes A.

Areas of Review Standard Format Section FSAR Section 3.1 Appendix 3D.1 3.2.1 3.2.1.3 3.3.1 3.3.1 3.3.2 3.3.2 3.4 3.4 3.5 3.5 3.8.1 3.8.1

3. 8.1(1) 3.8.1.1

3. 8.1 (2 )

3.8.1.2 3.8.1(3) 3.8.1.3

3. 8.1 (4 )

3.8.1.4

3. 8.1 (5) 3.8.1.5

3. 8.1 (6 )

3.8.1.6 3.8.1(7) 3.8.1.7 3.8.2 3.8.2

3. 8. 2 (1) 3.8.2.1.1; 3.8.2.2.1; 3.4.2.3.1

3. 8.2 (2) 3.8.2.1.2; 3.b.2.2.2; 3.8.2.3.2

3. 8.2 (3) 3.8.2.1.3; 3.8.2.2.3; 3.8.2.3.3

3. 8.2 (4) 3.8.2.1.4; 3.8.2.2.4; 3.8.2.3.4 i

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r JAN 2 M 3.8.2 (5) 3.8.2.1.5; 3.8.2.2.5; 3.8.2.3.5

3. 8.2 (6) 3.8.2.1.6; 3.8.2.2.6; 3.8.2.3.6

3. 8.2 (7) 3.8.2.1.7; 3.8.2.2.7; 3.8.2.3.7

3. 8.2 (C) 3.8.2.1.8; 3.8.2.1.9; 3.8.2.1.11; 3.8.2.2.8; 3.8.2.1.10 B.

Sections Where Sufficient Subject Matter Not Provided (Numerals refer to the SAR Format) 1.

Section 3.8.1(1) - For structures other than con-l t=inmant, design bases should be stated.

2.

Section 3.8.1(4) - Effects of an accidental drop of a fuel cask on spent fuel pool should have been l

investigated.

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