ML20140H464
| ML20140H464 | |
| Person / Time | |
|---|---|
| Site: | 05000231 |
| Issue date: | 09/04/1970 |
| From: | GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20140G249 | List:
|
| References | |
| FOIA-97-34 NUDOCS 9705130149 | |
| Download: ML20140H464 (16) | |
Text
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- i 5. R. R. SMITH & C-'B. DOE, CCLADDING FAILURE' T.MULATION TESTS IN EBR-II," ANL-70 67, DECEMBER , 19 66.
-' .R.R. SMIT,M, .ET AL., " LOCATING AND IDENTIFYING THE SOURCE OF THE 6
MAY 245 1967 FISSION PRODSCT RELEASE IN EBR-II," ANL-7543, APRIL, I
zu- _7. F. M. FRYER, ET AL., " SYMPTOMS AND DETECTION OF A FISSION. PRODUCT
\
,, . RELEASE FROM AN EBR-II FUEL ELEMENT \ CASE 1. DEFECT ABOVE FUEL ELEVA- i
.w>
. , l
- y. . TION," ANL-7 605, JANUARY, 1970.
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t l ', ' 8. I. A.'EFIMOV, ET AL., " ISOTOPIC COMPOSITION OF FISSION PRODUCTS IN l ....
s ~'!HE GAS OF THE FIRST CIRCUIT OF A BR-5 REACTOR WITH URANIUM 1 l
"2
~ MONOCARBIDE FUEL," TRANSLATION FORM ATOMNAYA -
ENERGIYA, UNDERSCORE LAST l .Q:q v. _
,,, . ,1W0 WORDS , VOL. 26, No. 6, PP. 544-54 6, JUNE, 19 69.
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,, 3.10 APPROACH TO' POWER
", APPLICABILITY -
.[, APPLIES TO REACTOR POWER LIMITS DURING THE INITIAL APPROACH TO FifLL iO POWER'FOR CORE I AND ALSO FOR CORE II.
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t hjg. 10 PROVIDE A. METHOD OF ASSURING A SAFE AND ORDERLY APPROACH TO FULL
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,$6 , E Ar 4 REACTORjPOWER[SHALL.'BELIMITEDT0'2MWTINITIALLY.'THIS, LIMIT
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if% . .fe:SHALL' BE SUCCESSIVELY INCREASED T0. VALUES OF 5,"10, 15, 17 5 4k)AAC49.W , a "
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. % p:,A.. r,MDIS,O5NWT7PROVIDEDJTHE.; CON,D,ITIONS. L?STED IN SECTION'3.3C,.D & E g \-
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,3R$jATIjlFiEB;%Ty,.EAch' 0F.TNES,E LIMITS JN jNEJPRR0ACH .TO , RATE 5 ' FLUX p.
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T REACTOR STABILITY Y L BE DETERMINED BY MEANS CONVENTIONAL OSCILLA-
,,' TUR TESTS AT EACH STEP IN THE APPROACH TO POWER. THESE TESTS WILL 00NSIST OF MEASUR,ING REACTOR FLUX AND INPUT REACTIVITY AS A FUNCTION pb ' 0F TIME WHILE THE REACTIVITY IS OSCILLATED AND COOLANT FLOW RATE IS
,f.. ,
HELD 'C'ONSTANT.
DATA FROM THESE TESTS WILL BE USED TO MAKE NYQUIST PLOTS FOR EACH POWER LEVEL.
= 4 l
l ~[ GUINEA PIG FUEL RODS \REF.1\ CONTAINING FUELPELLETS OF 25\ FISSILE l SP; . .
g PLUT0NIUM VILL BE PLACED IN THE. CORE AT POSITIONS LOCATED UNDER-lif)'THROUGHHEADREFUELINGPORTS,ANDWILLBEREMOVED'FOREXAMINATIONAT SCHEDULED INTERVALS IN TE TEST PROGRAM. UP TO THREE OF THE' GUINEA I PIG RODS WILL OPERATE AT POWER DENSITIES UP TO 15\ HIGHER THAN A
~
'~ STANDARD R0D NEAREST THE CENTER OF THE CORE.
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.c., THE SPECIFIED GUINEA PIG R0D EXAMINATIONS AFTER OPERATION AT POWER
! gggp 4EVELS .0Fi15 AND :17 5.MWT: WERE CHOSEN SUCH THAT SATISTACTORY OPERATING l
l h$ EdPERIENC$^VITH TEE lUINNA PIG RODS ~AT EACH OF THESE POWER LEV iy' H%%. w'L;. t ; en . T . .t Q@!gi. PROVIDEiASSURANCE 0F.lSATISTACTORY OPERATION OF STANDARD FUEL RODS AT I .
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C. THE REACTOR' POV'"1 LIMIT SHALL NOT BE INCRE' 'ED ABOVE 15 MWT OR AB0VE 17.5 MWT UNLESS ANALYSIS OF RESULTS FROM GUINEA PIG FUEL ROD l
EXAMIN TIONS SHOWS THAT NO DAMAGE TO STANDARD FUEL RODS IS TO BE EXPECTED BY OPERATION AT THE NEXT SCHEDULED POWER LEVEL.
D. 'A REACTOR HE'AT BALANCE SHALL BE MADE AS SOON AS PRACTICABLE AFTER ACHIEVING STEADY STATE POWER LEVELS OF 5, 10, 15, 17.5, AND 2d MWT,
~
10 DETERMINE THE CORRELATION BETWEEN RATED FLU AND REACTOR POWER.
l <
E. THE SPECIFICATIONS PREVIOUSLY IDENTIFIED IN THIS SECTION HAVEBEEN APPROVED AND ARE INCORPORATED INTO,THE SEFOR TECHNICAL SPECIFICATIONS l
l AS SECTION 3.L3. '\ PLACE BRACKET AROUND ITEM E ON RIGHT HAND .
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- 4.10-L, L4%.S.m6Pos.Es: CxANGE No. A. .
H Siik " sEPxsnaEn %.197of 1 ' [\PAGE NO. 'SHOULD V BE lI 3.10-1.\
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T.IIS. PAGE.IS INTENTIONALLY BLANK. \ PLACE BRACKET AROUND THIS SENTENCE C9.? - Gt RI'GHT MAND SIDE.\
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'PR5 POSED CHANGE NO. A
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M ytI " SEPT' EMBER 3, 1970
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A./qro EWOzA,TNE: REACTOR- POWER, tIMIT WILL BE. INCREA, SED IN A STEP-WIDE M ATIC.'AND'.0SCILLATOR MEASUitEMENTS MADE AT THE INDICATED ' POWER LEVELS.
TNE: RESULTS TROM TESTS AT EACH POWER. LEVEL WILL BE EVALUATED AND COM-( f*y%#} '.
W.c.3 ?.<,.;r, -
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s s. ED^@ PREDICTED RESULTS?AEFORE PROCEEDING 70iTNE NEXT HIGHER ' '
'- ' POWER
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. .7lRESULTS"FROM .$TATIC AND OSCILLATOjR' TESTS WILL BE ANALYZED TO
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" $ i. l n;.V 2 n .e % % > . J.IFY+TNAT;THEiMINIMUM .'~CONDITIONS'%:#. ?
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GUINEA PIG RODS NEI 'ST THE CENTER OF THE CORE WILL BE REMOVED PR
'dEACTOR OPERATION ABOVE.17.5 MWT, 50 THAT NO FUEL RODS WILL BE OPERATED AT POWER DENSITIES IN EXCESS OF THAT EXPERIENCED BY THE HOTTEST
- STANDAR,D F'UEL ROD AT 20 MWT. \SEE SPECIFICATION 3.3.H.\
?AK
- THE INITIAL CALIBRATION OF THE WIDE RANGE FLUX MONITOR WILL BE BAS THIS CALIBRATION WILL BE VER7FIED BY EXPERI-y g.4 0N ,',pYSICS CALCULATIONS. '
}%)$jk[lENTAL h DATA AS S00N AS PRACTICABLE, AND W f f 3PECIFIED. STEPS IN THE APPR0ACH TO POWER.
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~.. M . REACTOR OPERATING DATA AND EXPERIENCE UP TO AND . INCLUDING 10 M -
ty pese .
F E ED TO ESTABLISH ALLOWABLE LIMITS FOR UNEXPLAINED REACTO
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- SECTION.3.13 UAS ADDED.To THESE' SPECIFICATIONS TO SPECIFY THESE LIMITS. g hI
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, 8. .A COVER GAS M'ONITOR INDICATION GREATER THAN 10 TIMES g.jQsd/.a . .,
- gqip. c,NDRMAL, BACXGROUND AT THE IND,ICATED POWER LEVEL AND THE PRESENCE 0F N0BLE GAS ISOTOPES IN THE C0VER GAS SHALL BE CONSIDERED A i
i ${[],7 POSSIBLE INDICATION OF FAILED FUEL. TWO OR MORRE GUINEA o,
4
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- 19 ql6l6.P,IG~ ROD.S SHALL BE EXAMINED IN ADDITION TO THE SURVEILLANCE
! p. . . ., ,
l! dlfREQUIRED BT:= 4 9.B.4, AND 4 4.P. SUBSEQUENT REACTOR OPERATIONS
- f. 49.il, *:<
- }.y 6WILL BE ' ALLOWED, PROVIDED THAT THE INVESTIGATIONS ' CONCLUDE IT 1 f;. f
- .5 SAFE.T0' PROCEED \USING THE STEPS OUTLINED BT.THE
~ ~
4.9.B\. , ,
[E htESPONSE To ADDITIONAL FISSION Gf.S RELEASES TO THE COVER GAS
- .ysy g . a . . . -
. WILL FOLLOW THE PROCEDURES OUTLINED IN 4.9.B, UTILIZING THE j; ?*i'"WIINFORMATION OBTAINED FROM THE INITIAL RELEASE.
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J REFERENCE
. kDSAR, VOLUME I, PARA. 4.2.2.4, P. 4-9.
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3.10-3, PR6 POSED CHANCE NO. 4 SEPTEMBER 3, 1970
.vM, i START NEW PAGE 5h om' f; .
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.g , J :, 3 13 OPERATING LIMITS
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,'. APPLICABILITY
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.7 ' ,. APPLIES v e. , ,-.
TO PARAMETERS OBSERVED OR MEASURED DURING STEADY STATE '
Ah. ., RE, ACTOR
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OP.ERATION.
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$h..[ ANOMALOUS'.RENCTOR TBI'HA'VIOR AND 70 ' ESTABLISH -LIMITS FOR STEAD
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. v SPECIFICATION 1-1 .
- A. THE LIMITS FOR UNEXPLAINED BEHAVIOR SHALL BE AS GIVEN BELOW.
IF.THESE LIMITS ARE EXCEEDED, THE ACTIONS SPECIFIED IN SECTION cf' ' 4.9.B SN'ALL BE TAKEN.
4 ,
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- 1. A GROSS COVER GAS MONITOR INDICATION GREATER THAN NORMAL W ' BACKGROUND BY A FACTOR OF THREE AT THE INDICATED POWER LEVEL
- x
"- SHALL;BE CONSIDERED ANOMALOUS. IF IT IS DETERMINED THAT IT IS l q:y".j
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.S fjp..AFEToRESUMEREACTOROPERATIONS\USINGTHESTEPSOUTLINEDIN i 'c."
4.9.B.1\ OPERATION MAT BE RESUMED FOLLOWING.THE SELECTION OF A
> NEW LIAIT FOR THE GROSS COVER GAS MONITOR WHICH WILL ASSURE 3
- THAT AN EQUIVALENT RELEASE OF FISSION GAS FROM ANOTHER FUEL R0D
^
+ WILL BE DETECTED. THE NEW LIMIT SHALL BE REPORTED IN THE ,
i ;, ,! ? 'QUARTERLT OPERATIONS REPORT.
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' 3. ' A CHANGE IN STIADT STATE REACTIVITY OF - . " .MORE THAN PLUS OR l j M$.,r..
D,.NINUS 10. CENTS FR0N 'THE PREDICTED VALUE AT THE REACTOR OPE s
c - n;ps%;:r.n.ING.
- . CON.DITIONS SHALL BE CONSIDERED AN0MALOUS.
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f{h y!"A CHANCESIN-NAINiPRIMART COOLA
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. 4p LMINUS110V ux; w. y y: .FROM THE.PREDICTEDsVALUE .,n
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WHEN THE~C0OLANT FLOW Y,?? Y', >
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'ER ERnTHAN (1990? GPM S. HALL' BE CONSIbEREDiAN0NALOUS.; "' '
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iRESISTANCEjfENPERATERE9..
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BASES
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THE' REACTOR AND AUXILIART SYSTEMS NINCLUDING THE RADWASTE SYSTEM ^^
^
, HAVE BEEN DESIGNED So THAT STEADT STATE OPERATION WITH FIVE~
FAILED FUEL RODS CAN BE ACCOMMODATED \REFS.1,2\. THE C0VER GAS MONITOR IS CAPABLE OF DETECTING LOSS OF CLAD INTEGRITT IF IT OCCURS \REF. 3%. THE COVER GAS MONITOR WILL ALSO RESPOND TO FISSION PRODUCTS ESCAPING FROM PIN HOLE LEAKS, WHICH MAY OCCUR IN SOME FUEL RODS BUT WHICH ARE NOT CLASSED AS FAILURES \REF.
4\. THE NORMAL COVER GAS ACTIVITY DUE TO A-41 WILL BE ABOUT
.024 MICR0 CI/CC AT 20 MWT, AND THE CORRESPONDING INDICATION ON THE COVER GAS MONITOR WILL BE ABOUT 20 MR/M. IF 1\ OF THE 20 MWT EQUILIBRIUM FISSION PRODUCTS FROM A SINGLE ROD WERE RELEASED TO THE COVER GAS, THE COVER GAS ACTIVITY WOULD INCREASE BY ABOUT 3 MICR0 CI/CC, \REF. 5\ WHICH THE NORMAL IS A FACTOR OF MORE THAN 100 ABOVE THE NORMAL READING.
COVER GAS ACTIVITY MAY INCREASE OVER A LONG PERIOD OF TIME DUE BY TO THE POSSIBILITY OF PIN HOLE LEAKS IN SOME FUEL RODS.
l LIMITING ANY UNEXPLAINED INCREASED IN THE COVER GAS MONITOR l
READING TO A FACTOR OF THREE TIMES THE NORMAL READING, THE ,
g' CAPABILITY OF DETECTING NEW LEAKS AND/OR CLADDING FAILURE IS p ASSURED.
_ .- ..~.-.- - . . - . - .--.-.- .- . . -
0 START-NEW PAGE REPEATABILITY CONSIDERATIONS, BUT IS SMALL ENOUGH TO DETECT o
, INCIPI.ENT PROBLEMS BEFORE THEY HAVE A DETRIMENTAL, EFFECT ON REACTOR COOLING.
lsyt , _
ih7/>BECAUSE-THE OUTLET TEMPERATURES VARY SO WIDELY OVER THE COURSE
'N,h.[0F. THE..EEPERIMENTS, IT IS NECESSARY TO MAVE CRITERIA WHICH WILL ggr.y; v .
i;; C BE APPLICABLE TO ALL CONDITIONS. THE COMPARISON BETWEEN THE x1 >
y
..;hi ' VESSEL EEIT RTD\S AND THE. UPPER REACTOR . VESSEL OUTLET TEMPERA-
~>.
THE ALLOWABLE
.M^ .~
hgm. .. 'TURES PROVIDES A CROSS-CHECK .ON BOTH I h$ '. VARIATION VAS OBTAINED'BY EXAMINING THE DIFFERENCE BETWEEN THESE
,: ; \
$g'6i'c,NO TEMPERATURE DEVICES" OVER. THE TESTING COMPLETED UP TO 10 MWT, e
g%pg[EOCLUDING $THE NATURAL CIRCULATION S TE 7:S. THE VALUE OF PLh5 p . ,.
!vy x$@MINUS s, 80 DEGREE F IS;SLIGHTLY LARCER '. THAN ANT.
( g ne i V.3 2, ,
CALCULATIONS INDICATE THAT FOR FULL FLOW, t .
iQ A0BTAINED TO,DATE. g wi . .x . . K : . . . . . . . .,
L1? POWER';7TWERE SMOULD'BE'12 DEGREE T h DIFFERENCE FOR THE.AS-k&Nf WW < W.it > A V': A% . % .
w M@W@/COREU-M516BEq A DIFTERENCEDINTHESE. .'
TEMPERATURES OF
"~
M%Wi:44n..;M M: h. n . ..r 2- wL' .
FCOR ESPOND TO APPROEIMATELT 35\'0F THE,. TOTAL VESSEL TLCW
~
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eCOREc00NPARED 79 THE DESIGN. CONDITION OF 10\ BYPASS W: W i.& 2, '. M'w : .. . v' '-
. p VCOUL3NAL50:BE CAWSED.BT& CHANGES: IN FLOW DISTRIBUTION ,y 2'
- M: P.i+M 9 % ,
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.r#,%%QWh(ATsLON If181NG.'. EFFECTS FLOW RATES.< ,
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THE'SEFOR REACTOR OPL . TES OVER A WIDE RAN':E OF MPERATURE AND
. ' , POWER CONDITIONS IN THE COURSE OF THE DEFINED EXPERIMENTAL PROGRAM. TO FOLL,0W NORMAL EXPERIMTNTAL REACTOR CONDITIONS 4
REQOIRES A PREDICTIVE CAPABILITY FOR A BROAD RANGE OF CON-7 DITIONS. TO ESTABLISH DEFINITIVE CRITERIA FOR ANOMALOUS REACTIVITY, CAREFUL REACTIVITY BALANCES AD COMPARISONS HAVE BEEN MAINTAINED DURING ZERO POWER TESTING, FUEL ARRANGEMENT
. L
- , AND THE POWE* ASCENSION TO 10 MWT. .
INCONSEQUENTIAL RAND 0M t
l ,@ AND SYSTEMATIC ERP. ORS NORMAi.LY ARE LESS THAN THE PLUS- OR u c ,
j "[, . c MINUS 10 CENTS MAXIMUM DISPARITY BETWEEN PREDICTED AND l - MEASURED REACTIVITY VALUES. THE LIMIT IS RESTRICTIVE ENOUGH
.es TO ALERT THE OPERATOR AND STAFF TO ITEMS OF CONSEQUENCE, E.C.,
. e. s l
t SIGNIFICANT CHANGES IN THE REACTOR. COEFFICIENTS, ERR 0NEOUS
.e , , J11EL ARRANGEMENTS OR OTHER PROBLEMS.
t ,
1 A^ 4 COMPARISON OF THE COOLANT FLOW RATE TO THE PUMP CHARACTERISTIC y p>. .
'
- PROVIDES A CROSS COMPARISON BETWEEN THE PUMP PERFORMANCE AND ,
'y@:e.l f '1ME MAGNETIC'FLOWNETER.. THE PLANT IS PROTECTED..FROM ABRUPT AND_
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wn. ,ARGE LOSSES'0F. FLOW BT.THE LOW 'FL, OW -TRIPS AT 80\ OF THE SET . POINT MMhEl FLOW RATE.. ,TNE REQUIREMENT FOR COMPARIS0N OF. NEASURED FLOWL
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NffkPREDICTEDiFLOWWILLALERTTHEOPERATORTO).ANYDETERIORATION t ga y. p 6wa. ...w L .: .
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! SEPTEMBER 3, 1970 l
o EN CORRECTIONS \
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PAR. IV. A.1, LINE 2\ ---DUE TO A-41 ACTIVITY l
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PAR. IV. A.2, LINES 6,7\ ,
-260 LN \1 \ \77 P/\460 \ T SUBSCRIPT C\\\ -
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IV. A.2, ; LINE 11\ y ,, '
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'T SUBSCRIPT C \ AVERAGE CORE C00LANT TEMPERATURE
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/. GAS , RELEASE FROM . FUEL RODS IN THE SEFOR SYSTEM. THE RESPONSE TO ANY' ADDITTTTTIONAL INDICATIONS OF FISSION GAS RELEASE WILL DEPEND '
. 1 ON THE NATURE OF THE RELEASE AND THE INFORMATION OBTAINED FROM l THE INVESTIGATIONS OF THE INITIAL RELEASE. l l
1 i- REFERENCES l
s . <
s 1., SEFOR TECHNICAL SPECIFICATIONS, P 3.7-4, BASES FOR 3.7.H.
.P.
. +
t
- 2. SEFOR FDSAR, SUPPLEMENT 21, SECTION I.
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. 3. ' SEFOR FDNAR, SUPPLEMENT 21, SECTION II.
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. r. , 4 Q. 4.'. SEFOR TECNNICAL SPECIFICATIONS, PP 3.5-5,6, BASES FOR 3.3.K.
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- .SEFOR FDSAR, SURPLEMENT 21, P 14.
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' l FOR-EXAMPLE, ON THE BASIS OF PREVIO'US REACTOR \RA s0 DIE \ AND
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