ML19296A094

Requests Confirmation of Additions to ECCS Design. Changes Include Protection Trip Interlocks for HPI & Automatic Decay Heat Removal

ML19296A094
Person / Time
Site:	Midland
Issue date:	12/18/1978
From:	Novak T Office of Nuclear Reactor Regulation
To:	Satterfield R 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, FOIA-80-555 NUDOCS 7901040097
Download: ML19296A094 (1)

Text

N

,cM 4,

^

UNITED STATES NUCt. EAR REGULATORY COMMISSION y'

E

% $,l Q( /

WASHINGTON, D. C. 20555 A, //

%; '.O A fl Docket Nos. 50-329/330 DEC 181978 MEMORANDUM FOR:

R. M. Satterfield, Chief, Instrumentation and Control Systems Branch, DSS FROM:

T. M. Novak, Chief, Reactor Systems Branch, DSS SUB1ECT:

MIDLAND ECCS PUMP TRIPS The Midland ECCS design diffe' rs in some respects from similar previously licensed 177 Fuel Assembly B&W plants.

The applicant's response to RSB question 211.115 describes tt;.;e differences.

The design includes (items 2 and 8 in their response):

1.

protective trip interlocks for the HPI/ makeup pumps for normal operation to protect against misaligned valves.

2.

automatic decay heat removal /LPI pump trip on low flow to prevent pump damage due to inadvertent slosure of a suction valve.

We request that ICSB confirm that these " additions" to the Midland ECCS are acceptable, such that a single failure will not cause loss of more than one ECCS train.

5h Thomas M. Novak, Chief Reactor Systems Branch Division of Systems Safety cc:

R Tedesco

'.7a n i e s7 T. Novak S. Israel G. Ma: etis S. Newberry

Contact:

Sc.ott Newberry, NRR 49-27341 190l640 097

'