ML19275G904

Requests Evaluation of TRAP2 Code Used in FSAR Analyses of Steam Line Break,Feedwater Line Break & Loss of Feedwater Flow & Update of Position Re Cadd,Radar & Power Train Codes

ML19275G904
Person / Time
Site:	Midland
Issue date:	07/25/1978
From:	Novak T Office of Nuclear Reactor Regulation
To:	Rosztoczy Z Office of Nuclear Reactor Regulation
Shared Package
ML111090060	List: ML19208A315 ML19208A325 ML19250B014 ML19250B445 ML19250B480 ML19250B482 ML19254C975 ML19254G119 ML19254G128 ML19255K396 ML19255K397 ML19257E274 ML19257F047 ML19257F050 ML19260B823 ML19260E912 ML19260E913 ML19260E914 ML19261C469 ML19262E467 ML19262F230 ML19263D836 ML19263F605 ML19263G068 ML19268C086 ML19268C087 ML19269F130 ML19271A085 ML19271A172 ML19273B051 ML19273D308 ML19274A409 ML19274E085 ML19275B428 ML19275B444 ML19275C327 ML19275C328 ML19275G904 ML19275G918 ML19275H308 ML19275H317 ML19275H339 ML19275H341 ML19275H375 ML19275H401 ML19275H405 ML19275H493 ML19275H655 ML19275H660 ML19276D594 ... further results
References
FOIA-80-515 NUDOCS 8006200858
Download: ML19275G904 (1)

Text

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Docket No. 329/ 30 JUL 2 5 $78 Newberry chron U

MEMORANDUll FOR:

Z. R. Rosztoczy, Chief. Analysis Branch, DSS FROM:

T. M. Novak, Chief, Reactor Systems Branch, DSS

SUBJECT:

BABC0CK & WILC0% CODE REVIEW Reference]:

Memorandum for T. M. Novak from Z. R. Rosztoczy l

dated October 11, 1977 i

RSB is currently conducting the second round review on Midland 1 and 2.

The Midland FSAR Chapter 15 analyses -of steam line break,-feedvater line break, and loss of feedwater flow utilize the TRAP 2 code. My memorandum to you of March 30, 1976 requests the review of TRAP 2 which was also used in BSAR-205. We request that you provide us with your evaluation of the TRAP 2 code.

In addition, reference 1 provides RSB with your position with respect to the CADD, PADAR, and POWER TRAIN codes which are also used in the Midland FSAR. We also request that you fonfirm or update your position with respect to these codes.

orunet sinoat n Thomas M. MM EW Thomas M. Novak, Chief Reactor Systems Branch Division of Systems Safety cc:

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