ML20140H446

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Application for Amend to License DR-15,proposed Change 4 for SEFOR
ML20140H446
Person / Time
Site: 05000231
Issue date: 09/04/1970
From:
GENERAL ELECTRIC CO.
To:
Shared Package
ML20140G249 List: ... further results
References
FOIA-97-34 NUDOCS 9705130142
Download: ML20140H446 (7)


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PROPOSED CHANGE NO. 4 Y'+'

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-AA IIIo PURPOSE OF THE, PROPOSED CHANGE

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ShECIFICATION3.10-EOFTHEPREfiiNTSEFORTECHNICALSPECIFICATIONS REQUIRES THAT CERTAIN ADDITIONAL SPECIFICATIONS BE APPROVED AND

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' OPERATION AT '20 MWT.- TOESE SPECIFICATIONS ARE SUBMITTID HEREWITH,

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l COVER GAS. MONITOR HAS BEEN DEMONSTRATED AS REQUIRED BY 3.3.L OF j

THETENNICALSPECIFICATIONS\\HOWEVER,THEREISNOOPERATINGEI-

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1 PERIENCE WITH LEAKY FUEL RODS THAT CAN BE USED TO ISTABLISH FIRM QUANTITATIVE LIMITS ON ACCEPTABLE COVER GAS ACTIVTY LEVELS, COM-POSITION 0F FISSION PRODUCTS IN THE COVER GAS, OR' FISSION PRODUCTS l

L.

EXPERIENCE WITH OPERATING FAST-SPECTRUM SODIUM-j.Q p.

IN THE. SODIUM.

i %p.,

000 LED OIIDE' FUELED REACTORS '\\REFS.1 AND 2\\ INDICATES THAT LEAKY 4.;,

c,ey. FUEL RODS. SHOULD BE EXPECTED BUT THAT CONTINUED OPERATION IN THE 4

I i'M ; PRESENCE OF " LEADERS" DOES NOT PRESENT A SAFETY PROBLEM.

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TIONS WILL INDICATE THAT THE OBSERVED INCREASE IN COVER GAS I

ACTIVIT'l WAS THE RESULT OF A PIN HOLE LEAK It' FUEL ROD AND REACTOR j

g e WERATIONS WOULD IESUME.

IT IS ALSO POSSIBLE THAT ADDITIONAL IN-x

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. REQUIRED TO OBTAIN SUFFICIENT INFORMATION TO ALLOW RESUMPTION OF

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NORMAL REACTOR OPERATION.

SUBSEQUENT REACTOR OPERATION WILL REQUIRE T,. s,

lbek CAREFUL SURKEILLANCE OF GROSS COVER GAS ACTIVITY AN j

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E 1ME SAFETT SIGNIFICANCE 0F OPERATING WITH AN UNDETICTED FUEL R0D J

p 3,,') ' ' FAILURE HAS _BEEN DISCUSSED PREVIOUSLT \\REF. A\\.

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( 5,'. ;INLSUMNART, SEFOR R,AS BEEN SUCCESSFULLY.0PERATED To A sPOW]

.e e m, T 5.:MUT.3WI,,TH..O. U.T. INDICATION' 0F LOSS OF CLAD.INTEGRITT.

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THE PROPOSED LIMITS N ANOMALIES OTHFR THAN THf ASSOCIATED WITHTHE REACTOR COVER GAS ACTIVTY ARE BASED CN ACTUAL OPERATING EXPERIENCE AT SEFOR.

AS DISCUSSED IN THE BASES FOR THESE PROPOSED LIMITS, THE VALUES HAVE BEEN SELECTED SO THAT THE PROPER ACTION IS TAKEN ON VARIA-TIONS' THAT ARE STATISTICALLY SIGNIFICANT.

ACTIONS TO BE TAKEN IN THE i

. EVENT ANY OF THE PROPOSED lit:ITS ARE REACHED ARE COVERED IN 4.9 0F THE TECHNICAL SPECIFICATIONS.

l REFERENCES \\

1.

G. KAYSER,'" PROBLEMS DUE T0 FISSION PRODUCTS IN CIRCUITS OF SODIUM-COOLED FAST REACTORS IN THE EVENT OF CAN FRACTURES," ZUEFNR-l 593 \\0RIGINAL REPORT NO. DRP/SEMTR/ CAD.65.R.575\\, NUCLEAR 5ESEARCH l

CENTER CADARACHE AND SACLAY \\ FRANCE \\, DECEMBER,1965.

j l

2.

A. I. LEIPUNSKII, ET AL., " EXPERIENCE GAINED FROM THE OPERATION OF t

s L

' 1HE BR-5' REACTOR, 1964-5,8 PAPER 2/3'0F PROCEEDINGS'0F,TNE LONDON M. s.

CONFERENCE ON FAST'BREEDE5 REACTORS, MAY,.1966, PP'171-185-e t

gp,i 3

t jff [ 3.

.DR.. STANLEY J. ' STACHURA \\CADARACNEiREPRESENTATIVE,' AEC-EURATOM

..Yk$T REACTORJEICH NGE PROGRAM \\,. 'MbhTIN. HEP RT NO.48,',"Nnh(( JU h

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