ML20234C355
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UNITED STATES ja
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ATOMIC ENERGY COMMISSION e
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WASHINGTON, D.C.
20545 i.
February 8, 1973
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-Docket Mos. 50-2374 50-249,30-254 and 50-265
. M.
03 Mr. Harold G. Mangelsdorf Chairman, Advisory Committee on Reactor Safeguards U. S. Atomic Energy Coc: mission Washington, D. C.
20545
Dear Mr. Mangelsdorf:
Sixteen (16) copies of the following are transmitted for the Committee's information:
Letter from Commonwealth Edison Company dated January 24, 1973, transmitting Special Report No. 19 f or Dresden Units 2 and 3 and Special Report No. 6 for Quad-Cities Units 1 and 2 entitled "Feedwater Control System Modifications".
Letter from Commonwealth Edison Company dated January 26, 1973, furnishing additional information relating t.o the oxygen sampling systems for'Dresden Units 2 and 3 and Quad-Cities Units 1 and 2.
Letter to Commonwealth Edison Company dated February 2, 1973, requesting analyses of the consequences of a control rod drop accident at Dresden 2 and 3 and Quad-Cities 1 and 2.
Sincerely, 7
gl h'd h Donald J.
Kovholt Assistant Director for Operating Reactors i
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Directorate of Licensing l
Enclosures:
As stated
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THOMASB7-40 PDR
OFFICIAL USE ONLY SUP?IJ22:C NO. i e CATEGOKY B k
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i Dresden Units 2 & 3 loa.ad Cities 1 &_2 Esrch 2,1973 f
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E Fa d nter O m rol 6ystes _
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1 ACRS C-.7-m it6 7. e-e we 1*tter dated J.tnearv 2.*.,
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- cr Control Systea l'ia ilic at. c ~
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- r..,lans contributed to t'c a ;c r e :d.
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...::ica it.eincnts :r.at have resulted ft:m cafec" - U e s:na. m.
La t adii1:ations have been r.J.2 en i c.v :n Unit ". c.c.l C. tad Cities Unit 2 with a de=onstrated i=proverent in response.
No ACRS action is reconunended.
The enclosed e.aterial should be retained as part of the l
permanent record.
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0'evwn Semie Systes ACRS Comewenith Eiisen Cc.many letter dated January 26. 1973 responcs to L.:/L letter dated 1.ovember 15, 1972 requesting additional infor:ation re,narding the oxygen analyzer cystems.
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The troubles enperiented to date relate to lack of lubrication i
on valve sten.J nrci a prcaram et periodic lubrication has been established. An en;;ineering review is being made to assure that a system failure will not result in direct lankage from
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the containment.
No ACRS action is reconsnended.
The enclosed e.aterial may be discarded after your review.
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Rod Drop Accident Analysis ACRS A"0/L 1etter dsted February 2,1973 requests an analysis of the rod crop acercent icr core loadings similar to those currently used in Dresden Units 2 & 3 and Quad Cities Units 1 & 2.
The
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Staff finds that it is not apparent that either I C O-10527 or its Supplement 1 are precisely applicable to these core con-
' figurations. Maximum rod worths are also requested assuming one operator error.
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No ACES action is recommended.
l The enclosed meterial may be discarded after your review.
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