ML20126H387

Approves Proposed Change to Facility FSAR Section 8.3.1.4.1.1.e

ML20126H387
Person / Time
Site:	Wolf Creek, 05000000
Issue date:	02/15/1985
From:	Srinivasan M Office of Nuclear Reactor Regulation
To:	Youngblood B Office of Nuclear Reactor Regulation
Shared Package
ML20126H338	List: IA-85-160, Trip Rept of Site Visit During Wk of 831031 Re Physical Arrangement & Installation of Electrical,Instrumentation & Control Equipment.Compliance W/Nrc Design Criteria Confirmed IR 05000482/1984051 ML20126H335 ML20126H387 ML20126H439 ML20126H482 ML20126H603 ML20127B510
References
FOIA-85-160 NUDOCS 8506100324
Download: ML20126H387 (1)

Text

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/pis,,*% UNITED STATES ,

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' jj NUCLEAR REGULATORY dOMMISSION WASHINGTON, D. C. 20$55

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6.** FEB 151985 '

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,MEMORANhUMFOR:'B..J.Youngblood, Chief

- Licensing Branch No. 1 -

Division of Licensing FROM: M. Srinivasan, Chief Power Systems Branch Division of Systems Integration

SUBJECT:

WOLF CREEK PROPOSED FSAR CHANGE The Power Systems Branch has reviewed the change proposed to the Wolf Creek FSAR by Kansas Gas and Electric Company's letter dated January 14, 1985.

Specifically, the change inserts the following wording in FSAR Section 8.3.1.4.1.1.e:

o

- In cases of open trays containing safety-related cables and c totally enclosed conduits containing non-safety related cables, -

- the safetf design basis is to protect the safety related cables .

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from failure of the non-safety related circuits, and not vice-versa. In consideration of this limit, enclosing the non-safety

,L circuits in raceway and maintaining at leastJ-inch separation ,

provides an acceptable level of protection. The conduit can p . containonlyalimitedquantityofcombustiblematerial(cable i insulation & jacket).- All SNUPPS cables, including those used

• D9 for non-safety related circuits,.are qualified to IEEE-383 and meet the flame-retardance requirements specified therein; the cables will not support combustion. Furthermore, there is insufficient oxygen inside the conduit to support combustion of more than fraction of the available material. i c  :

E Based'on these considerations, it is established that 1-inch  !

4 separation between a conduit containing non-safety related circuits' .

l 1s sufficient to assure that any failure within the non-safety i related circuits will not propogate into and compromise the

,. integrity of the safety related circuits.

We have reviewed the justification for the proposed change and find it

. acceptable. .

f, f ft G6 i Wh_1 M. Srinivasan, Chief Power Systems Branch

• i mig r4e50415 Division of Systems Integration

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1 STEPHEN 85 -1g pg

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