ML19317F545

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Forwards App to BAW-1420, Fuel Densification Rept, Transmitted 750904.Info Withheld (Ref 10CFR2.790)
ML19317F545
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 09/30/1975
From: Suhrke K
BABCOCK & WILCOX CO.
To: Schwencer A
Office of Nuclear Reactor Regulation
References
NUDOCS 8001150858
Download: ML19317F545 (4)


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. NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL s

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Mr. A. Schwencer 5y Chief, LWR Branch 2-3

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Dear Mr. Schwencer:

v Enclosed are twenty copies of the Appendix to B&W report BAW-1420,

" Davis Besse Unit 1 - Fuel Densification Report." BAW-1420 was trans-mitted to you on September 4, 1975. This Appendix was inadvertently omitted during collation of the report.

Very truly yours, BABCOCK & WILCOX COMPANY Nuclear Posar Generation O

L Kenneth E. Suhrke Manager, Licensing KES/fw Enclosures

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o APPENDIX Identification of Proprietary Information Deleted for This Report A-1 babcock 8 WilCOX

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73 s,

This appendix identifies the areas where proprirPary information is included in the proprietary version of this report (BAW-1401) but bas been deleted for this version.

Section Page(s)

Description 3.2.1 3-4 TAFY input values.

Figures 3-7, Assumptions 1-5 deleted; assumptions 6 and 7 3.2-1, 3-8, renumbered 1 and 2.

3.2-2, 3-9 3.2-3 3.3.3.2 3-13 Reference to Table 3.3-2.

3.3.3.3 3-14 References to Tables 3.3-3 through 3.3-5.

Time and magnitude of peak.

Table 3.3-2 3-16 Entire table: Fuel Cycle Data - Equilibrium Conditions Table 3.3-3 3-17 Entire table: Four-Day Design Transient Data Table 3.3-4 3-18 Entire table: 200-Day Design Transient Data Table 3.3-5 3-19 Entire table: 375-Day Design Transient Data 3.5.1.1 3-35 Cladding ovality, cladding thickness, prepres-sure, and post-densification propressure.

3.5.1.3 3-35 Value for design lifetime.

Table 3.5-1 3-36 Entire table: Sunsnary of Fuel and Cladding Specifications.

A-2 B4bCock & WilCOX

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