ML20039H216

Forwards Reactor Fuels Section Safety Evaluation Input Re Status of ACRS Generic Item II-4 Concerning Instruments to Detect Fuel Failures

ML20039H216
Person / Time
Site:	05000561
Issue date:	04/13/1977
From:	Check P Office of Nuclear Reactor Regulation
To:	Stolz J Office of Nuclear Reactor Regulation
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References
FOIA-80-515, FOIA-80-555 NUDOCS 8201190729
Download: ML20039H216 (2)

Text

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NUCLEAR REGULATORY COMMISSION 7

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WASHINGTON, D. C. 20555 s-(s N

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MEMORANDUM FOR: John F. Stolz, Chief, Light Water Reactors Branch 1, DPM

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FROM:

Paul S. Check, Chief, Core Performance Branch, DSS

SUBJECT:

ACRS GENERIC ITEM II-4 STATEMENT FOR B-SAR-205 The Reactor Fuels Section has prepared the attached input.to the B-SAR-205 SER regarding the status of ACRS Generic Item II-4, Instruments to Detect Fuel Failures.

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Paul S. Check Chief, Core Performance Branch Division of Systems Safety Enc 1: As stated I

cc:

D. F. Ross R. Meyer T. Cox B. Siegel i

F. Coffman j

R. Lobel i

M. Tokar t

hR f[29810403 MADDEN 80-515 PDR

Enclosure APR ' 31977

,%; Item 11-4 Instruments to Detect Fuel Failures This item has been identified as partially resolved (letter, i

Bender to Rowden, February 24, 1977).

Instrumentation to detect j

fuel failures associated with normal operation and transieats (limited i

I fuel failures) has been shown to be adequate (see report, B. L. Siegel and H. H. Hagan, " Fuel Failure Detection in Operating Reactors,"

June 1976), and this portion of this matter is considered resolved.

l The adequacy of instrucentation to detect failures associated with more rapid events during which substantial fuel failure could occur 1

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has not yet been demonstrated and this second segment, therefore, is l

still considered unresolved.

Further work is necessary to determine (1) the adequacy of current instrumentation for these rapid events and (2) the need for additional. instrumentation.

Research adminis-tered by Reactor Safety Research (RSR) and studies conducted under contracts administered by Nuclear Reactor Regulation (NRR) should provide the information. required to evaluate instrumentation limitations and 1

needs.

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In the interim, since we have not been able to identify any l

credible event (transient or accident scenerio) that would lead to " substantial" fuel failure, including fuel melt, (and loss of I

coolable geometry) unless detected and terminated by a rapid fuel i

failure detection system, this item should not preclude issuance of a preliminary design approval.

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