ML20126E285

Submits Addl Info in Response to Questions Re Details of Accident Analysis Which Supports Request for Change 8 to Tech Specs.Substitution of zircaloy-clad Fuel for Stainless steel-clad Fuel Does Not Present Hazard

ML20126E285
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	05/02/1966
From:	Haueter R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	Boyd R, Doan R US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8101160425
Download: ML20126E285 (10)

Text

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H/$ RERUN 07 TUX NR 240

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-l CONSUMERS PO'tER COMPANY j PARNALL ROAD OFFICE TVX 517 787-1955 -

. JACKSON MICHIGAN e

5-2-66 5-00 PM G}.f,.Q [iQ CD -/CE* -- .-~

""*= V J  :

TO - DR. R. L. DOAN' DIRECTCR l

DIVISION OF.-- REACIOR LICENSING i l

UNITED STATES ATOMIC ENERGY COMMISSION .-

WASHINGTON' D.D.

ATTENTION - MR. ROGER S. BOYD

• i s .%

. t FROM -

MR. ROBERI L. HAUETER ED CONSUMERS POWER COMPANY

]y MAY3 aneuw, 1966 > 11 i

i

' DOCKET 155 e ..

4 h M # i i N < ,

I -

I THE FOLLOWING INFOPMATION IS SUBMITTED TO YOU IN REPLY To QUESTIONS f

ASKED BY DRL STAFF VIA TELEPHONE CONCERNING THE DETAILS OF THE ACCIDENT ANALYSES WHICH SUPPORTED OUR RECENT REQUEST FOR CHANGE -

)- '

$ NO. 8 - TO THE TECHNICAL SPECIFICATIONS OF LICENSE NO. DPR-6. AS

!' N"*

I O . STATED IN OUR ORIGINAL CHANGE REQUEST'WE HAVE CONCLUDED THAT THE I

t SCSTITUTION OF ZIRCALOY-CLAD FUEL FOR STAINLESS STEEL-CLAD FUEL DOES

! D :.;! PRESENT SIGNIFICANT HAZARDS CONSIDERATIONS NOT DESCRIBED OR IMPLICIT THE FHSR. AS WILL BE NOTED BELOW' THE NUMERICAL RESULTS OF THE  !

'%1 g,y ACC 3ENT ANALYSES DO CHANGE SLIGHTLY FROM FHSR VALUES BUT BECAUSE OF Q

"UI VERY NATURE OF THE CkLCULATIONS AND THE NECESSARY CONCOMITANT r ASS L__ _U.MPTIONS'. THESE CHANGES CANNOT

. _ - . . . . . =..--BE - -REGARDED

. - - . - - , AS - - SIGNIFICA.NT.

• l. ,CCNTRCL ROD DROP 4CCIDENT - HOT STANDEY CON" TION -

ONLY THE RCD DROP ACCIDENT VAS ANALYZED. THE ROD EJECTICN CASE- ,

IS NCT CCNSIDERED CEEDIELE SINCE THE E.1ITTLE FRACTURE CF A CCNTROL F 0D HOUSIN3 CR SIMULT ANECUS FRACTURE OF' ALL FLANCE EOLTS MUST OCCUR ,

SIGULTANEOUSLY WITH EITHER THE MAXIMUM POSSIELE OR THE MAXIMUM PRO-CEDURAL EDD VCRTH. -

A. RESULTS - >

TAELE I LISTS THE RESULTS OF THE VARIOUS ACCIDENTS  ;

ANALYZED. NOTE THAT' BASED ON OUR OPERATING EXPERIENCE-TO DATE' VE DO NOT CONSIDER THE 'MAXIMUN RCD WORTH CASES . ,

TO BE CREDIELE. TO ACHIEVE THE MAXIMUM ROD WORTH CON- {

FIGURATION

• SEVERAL PROCEDURAL CCNTROLS MUST BE VIOLATED DELIBERATELY. IT IS EXTREMELY DCUSTFUL IF ANY OPERATOR COULD DEVELOP A RCD PATTERN' STARTING FROM HOT STANDBY' .

THAT WOULD APPROACH THE NECESSARY CONTROL ROD CONFIGURA-TION FOR MAXIMUM RCD WORTH. THIS CONFIGURATION IS DIFFERENT EN00CHFROMTHETWOAPPROVEDRODWITHDRAVALSEQUENCESIh!'

USE AT BIG ROCK POINT THAT ITS OCCURRENCE AS A NONDELIE,ERATE EVENT MUST BE CONSIDERED INCREDIELE.

THE ANALYSIS OF DOPPLER LIMITED REACTIVITY INSERTION ACCIDENTS -

EXCURSIONS - WERE PERF,CRMED WITH A SYNTHESIS OF SPATI AL EFFECTS AND THE STANDARD SPACE-INDEPENDENT NEUTRON KINETICS EQUATIONS. THE METHOD CF ANALYSIS' IMPORTANT ASSUM?IIONS' AND RESULTS FOLLOV.

IT WILL EE NOTED FROM TAELE I THAT THE MAXIMUM CALCULATED ROD IN THE STAIHLESS-CLAD CORE WAS .042 DELTA X WHILE IT IS .046 DELTA K IN THE I

. ZIRCALOY-CLAD CORE. THE REACTOR LICENSE PROHIBITS OPERATING PATTERNS VITH RCD WORTHS EXCEEDING .025 DELTA K. THE FLEXIBILITY IN ACHIEVING OPERATINC PATTERNS'VITH RCD WORTHS LESS THAN .025 DELTA K IS SIMILAR l FCR THE TWO CORES. IN THE ZIRCALOY CORE' THE LARGER CORE VOLUME -

i HUR'.'ITI-ROE CONTROL AREA RULE - AND THE SLIGHTLY REDUCED INFINITE i.

! tLTIPLICATION CONSTANT - K INFINITY - 0F UNCONTROLLED FUEL MORE THAN COP.PINSATE FOR THE REDUCED K ILFINITY OF CONTPOLLED FUEL. 7 I

TAELE I -

SUMMARY

OF ROD DROP ACCIDENTS - HOT STANDBY CONDITION

.b w** 64* .*** ha- e ' *

.....+.-m4-' _ == w w ---e.,-n> **e.m~ =C mem*+ 4 w ' - =*

- CALCULATION EASED C;* CLDER GE METhCDS AND FP.SR PARAF.ETERS MAXIMUM R0D--

SS CORE ~ ZR CORE E0.

t. 0 .

1. DELTA K/K INSERTED .042 .04G

2. MINIMUM PERIOD

• MS 2.0 1.9

3. PEAK NEUTRON FLUX' TIMES RATED 6'250 3'10D

4. PEAK FUEL TEMPERA-TURE' F 13'900 12*S00

5. REACTOR PEAK POVER*

MYT 1.0 X 10 TO SIXTH .7 X 10 TO SIXTH

6. INTEGRATED ENERGY' .

M '.'- S E C 3'320 2.'S20

7. UO2 EXCEEDING 5000 F

-INCIPIENT MELTING -

LB 2'200 2'200

- E. UD2 EXCEEDING 360 6 CAL /GM- CLAD RUPTURE' LB 529 370

?

g 9. U02 IN RUPTURED FUEL RODS

• LB l*550 l*240 NOT NOT 1 10. CHEMICAL ENERGY FROM

! METAL-VATER REACTION t

MV-SEC ,,

C ALCL'L ATED , _ CALCULATED

11. GAS TROM METAL-VATER REACTION' SCF H2 110T CALCULATED NOT CALCULATED 1-l ..

t

(')-

CALCUL AT20N BASED O!' 'RI.SENT GE 11ETHODS ,

)

MAXIMUM ROD-- PECCEDUT.AL CONTROL SS CCRE ZR COEE SS CORE ZR CORE m

h0W NC. .

1

'  !. DELTA K/K It;SERTED .042 .046 .025 .025

2. MINIMUM PEPIOD*MS 2.7 2.6 3.7 3.7 ,

3. PIAK NEUTRON FLUX' ,

TIMES RATED 900 740 700 SEO

4. PEAK FUEL TEMPERA-TUEE' F 15'500 15'700 9'000 E*E00

5. RE ACTOR PEAK P0i'ER' MWT .14 X 10 TO .lE X 10 TO . IX 10 TO .14 X 10 0 SIXTH SIXTH SIXTH SIXTH

6. It:TECEATED Et;ERGY' M'.'- S E C KZCKK 3*770 2'200 2*700 2'S00

7. UD2 EXCEEDING 5000 F - INCIPIENT 2'4GO 450 510 MILTING - LB l'420 i '

?

i i

j E. UO2 EXCEEDING 360 I CAL /GM- CLAD 450 500 NEGLIGIBLr NEGLIGIE RUPTURE' LB ,

i 1 S. UO2 IN RUPTURED ,

l'500 3'160 NEGLIGIELE NEGLIGIEE FUEL ROD 5' LB i

}

10. CHEMICAL ENERGY FROM METAL-VATER 600 10 150 REACTIOS' MV-SEC 27

=== e -'

.,-,,,a,% ,,se e,- aw

• = Nee *=ema*-am . e e. se i. memesp . _ . _ _. ._

= *-  %

C'/ 11. CkS FFOM MITAL

. .. s, W ATE' REACTIO..

6SD I'SEO . 160 390 SCF H2'

~

-CORRESPOS;S 70 E00C F AS PRESENTED IN FHSR.

k l 1

--MAXICUM ROD WORTH CASE'NOT CONSIDERED CREDIELE.

THE PRESSURE IN THE PRIMARY SYSTEM DURING A REACTIVITY EXCURSION. 07-

$, THE MAGGITUDES LISTED IN TAELE 1 IS A CCT. PLEX DYNAMIC CUANTITY.

C ALCULATIONS INDI,CATE THAT FOR CASES WhERE THE FUEL DOES NOT EXCEID

~

E000 F - 3C0 CAL /CM - CONTINUED INTEGRITY OF THE PRIMARY SYSTEM VILL EE MAINTAINED.

i ,

THEEE APPEARS TC EE CONSIDERAELE.CONTECVERSY SURRCUNCING TME ASSUMP-TIONS CONCERNING.THE TRANSFER OF EXCURSICS ENERGY TO PRIMARY SYSTEM' VATER DURING MORE SEVERE EXCURSIONS VMERE A SIGNIFICANT AMOUNT CF: FUEL EXCEEDS 360 CAL /GM. SINCE NO CALCULATIONAL MODELS HAVE BEEN ACCEPIED FOR THIS TRANSIENT' VI CANNOT MAKE ANY MEASINCFUL STATEAENT RECAFDI:43 PRIMARY SYSTEM INTECRITY FOR THE ROD DROP CASES INVOLVING THE 4.2 OR 4.0 PERCENT RODS.

. ANALYSIS CETHOD t

t i THE L ATEJT ANALYTICAL TOOLS ' AND METHODS VER~ EMPLCYED THROUGHCUT- THE Pr.ESENT ANALYSES. THE CHANGES AND THEIR EFFECTS WILL BE DISCUSSED.

?

1. TO INCOTsPCR ATE REACTOR SPATI AL EFFECTS I';TO THE DOPPLER FEEDS ACK l

TO THE KINETICS CALCULATION' A SPACE-TIME KINETICS ANALYSIS IS SYNTr.ESIZED BY A MARCHING CALCULATION. . INITIAL NEUTRON FLUX DISTRIEU-TIONS ASSOCIATED WITH ACCIDENT _AL REACTIVITY ADDITION ARE FIRST l

j- DETERMINED UTILIZING A THREE-CROUP' STEADY-STATE DIFFUSION CALCULA-f TION. A CORE AVERAGED DOPPLER SPATIAL WEIGHTING. FACTOR IS ESTIMATED FROM THE FLUX DISTRIBUTIONS AND ' UTILIZED IN THE POINT' KINETICS EQUATIO l TO GENERATE A SMALL INCREMENT OF POVER. IN THIS CASE' THE KIKETICS CALCULATION REPRESENTS THE AVERAGE REACTOR CONDITION.

f 4

THIS' INCREMENT OF POWER' EXPRESSED AS A FUEL TEMPERATURE CHANCE' IS THEN SPATIALLY DISTRIBUTED ACROSS THE CCRE ACCORDING TO INITI AL FLUX

{

DISTRIBUTIONS. NEW SPATIALLY DISTRIBUTED CFOSS-SECTIONS ARE_ COMPUTE 0' T,ETLECTING THE D0' ER EFFECT DUE TO THE ADDED TEMPERATUREAND ANOTHER j

f

,+ .r . , - , . .- , , . . m, - . ,  %,,'br.

, ..w-v,- m,e.,,-rv, ,v. r v - w ,.e c-w--- .+ & . e- =v~w.-v ,- v'+*,-e .,

. - - . . m ._ ._ -. , . m , -_ _ _ . . --.

d DIFFU:'IONICALCULATIO:',JS MADE. C07.PARISON 0F, THE EIGEt4VALUE CHAN3E IN -

(

TMIS CALCULATION TO T ElGENVALUE CHANGE RESULh11 G Th05 L A Ui IFORMLY.

DISTRIBUTED TEr.PERATURE It1CREMENT'PF0VIDES AN ACCURATE ESTIP. ATE OF.THE DCFPLER EEICHTIN:; FACTOR APPF10PRIATE FCR THE NEXT KIHETICS CALCULAT10::AL

~

STP. UTILIIINC THIS PRCCEDURE' THE CALCULATIOh IS MARCHED THROUGH TO ItE TETJ,1NATICN CF.THE EXCUP.SION.: ,. j o

e THE PF,EVIOUS CALCULATIONS DID NOT INCLU;E THIS. SPACE-TIr.E MARCHINC-ECLUTION' BUT ASSURED A FIXED POVER SHAPE VITH FIXED : DOPPLER VEIGHT .  ;

i IN3 FACTOR THROU3HOUT THE' EXCURSION. THE SPACE-TIME DEPENDENT' CALCULATICf: INCLUDES THE INHERENT PCVER FLATTENIkG AS FUEL IS< HEATED t

IN THE ZONE CF THE DROPPED CONTROL BLADE. , ,

'e t +

[

t .

2. THE EXCURSIDIJ CALCULATION IE CT TERR,1NATED UNTIL TH" P0JER HAS

~

EEA0MED A SMALL FRACTION OF-RATED. PREVIOUS CALCULATIONS WERE TERF.I< j t

NATED AT 100 MS AFTER PEAK POWER' THUS ELIMINATING THE ADDITIONAL 20 TO 30 PERCENT OF ENERGY COSTAINED IN THE EXCURSION TAIL. THE TOTAL a

~,

INTECRATED ENERGY IS

• THEREFORE' L ARGER' 'THOUGH IT IS GENERATED CVER -

r

. EXTENDED TIME. PERIOD.

i

5. THE EXCURSIONS ARE ASSUT.ED TO EE ADIAEATIC W'ITH ONLY THE D0??iER. $}

EFFICT SUPPLYING PRCMPT REACTIVITY FEED 5A0K TO TER.':INATE THE. POVER -

BUF.?T. II: PAETICULAR' NO NEGATIVE FESD5 ACK FF.CM PROMP* f00]ERATOR q E ATING IS ASSUMED. THE MAG:JITUDE OF THE REACTIVITY EFFECT DUE 70 DOFFLER BP.0ADENING IS CCSEERVATIVELY TAKEN TO BE ABOUT 5 PERCENT LESC i THAN THAT RESULTING TECX USE OF PETTUS DATE - I'- AND 13 PERCENT LESS THAN THAT US'IN3 HELLSTRAND DATA - 2 . THE TEMPERATURE DEPENDENCE OF

-)

, THE DOPPLER COEFFICIENT USED IN ALL THE ANALYSES IS BASED ON THE SQUARE- .s .

1 ,

1 ROCT OF TEF.PER ATURE FORM. EXPERIMENTAL DATA FOR OXIDE FUEL ARE FIT M  !

PRECISELY BY THIS FORM IN BOTH DIFFERENTIAL MEASUREMENTE - 1*2'3 - AND i GROSS CORE DYNAMIC MEASUREMENTS - 4.

[

i -

i DOPPLER COEFFICIENTS ARE AFFECTED PRIMARILY BY WATER-TO-FUEL RATIO AND 70 A LESSER EXTENT BY FUEL' DENSITY AND GEOMETRY. BIG ROCX PDIN j FUEL TYPES ARE ALL SIMILAR IN THESE PARAMETERS AND' DUE TO C07.P 5

IFTECTS' ARE SIMILAR IN DOPPLER COEFFICIENT. THE 13 PERCENT DIFF l' IN DOPPLER COEFFICIENTS USED IN THE CALCULATICNS IN REFERENC i

I RELOAD AND STANDARD FUEL VAS CALCULATIONAL AND NOT A PHYSIC t

I . .. . t . s w. r. . .'s. . u . - . .  %,- .

i

+

• W e-emoe meeee,*ese, wen

• m m es=we en**-

m*** v we ew t -seep p eau.e, . _

ep. S 9---, *,- ..e  % w w E ,,, u .,-.we.,. , . - - - _ . - .,[.,~.m 3 ,,m'.-

r , , - , ,- , v~-e u  %,. p o,- -.

. . -. . . . - . . - . . . _ . . . . . ^ ^" '

W TlE' STANDARD FUEL COEFFICIENT"HAS BEEN' CORRECTED BY OSE'0FTA"MCRC ~^:

n.

. I.CCUht.TE EFFECTIVE ' SUEraCE-TC-MASS AND RES0"ANCE ..TEGR AL? TREATICEt:T.

IU - ADDITION' THE ZR CORE CALCULATIONS HAVE BEEN RE-EVALUATED.> THE-T l RESULTA"7 VALUE FOR BOTH FUEL TYPES IS .t:EG ATIVE l'.1 TIMES 10' TOI HE 8..

MIKUS 5 DELTA K OVER.K PER DEGREE ~F AND{IS.QUCTED11N.CHAN2E NO.

THE INITI AL POWER .IS ASSUMEC TO BE 10 TO THE MINUS 6 0FJ RATED IN

. . . . . .. < . }

4. .

t THE HOT STAT:DBY CONDITION. ' THE PREVIOUS : AN ALYSISl ASSUMED. '10' TO. THE'

\

HII;US 10. HOVEVER' RECENT CALCULATIONS REVEAL'THAT 10 TO THE MINUS:

{

6 IS THE MINIMUM SOURCE LEVEL AT,' HOT. ST ANDBY CONDITIONS. THIS IS THE 4

RESULTAN,T LEVEL D'UE TO SOURCE NEUTRON AND SPONTANECUS FISSION NEUTRON:

INTRODUCTION FOR THE LOWE'T. S CORE' REACTIVITY AT WHICH A PROMPT CRITICAL ,

i- A*CIDENT COULD. 0CCUR WITH A 0.046 DELT A X ACCIDENT.' THIS REACTIVITY

-INCREAS-IS APPROXIMATELY 0.961' AT WHICH CORE MULTIPLICATICH IS 25.'6. ,

. IU" It;ITI AL POWEP KESULTS 'IN A SLIGHT REDUCTICN IN ACCIDENT EEVERITY. '  !

5. REACTIVITY IS ADDED ON THE' ACTUAL l WORTH-DISTANCE RELATIONSHIP "E" CURVE' ASSUP.ING THE ROD IS FULL IN VHEN IT COMMENCES TO FALL.'- TH

~

PT.LVIOUS ANALYSIS USED A. MO.RE CONSERVATIVE APPROACH EY. INSERT ELACTIVITY AT THE MAXIMUM RATE AVAILAELE.

C. THE LOCAL PEAKING HAS.BEEN INCREASED TO REFLECT THE SPECIFIC P OF THE SMALL CORNER FUEL RODS. . THESE RODS. HAVE THE' HOTTEST c LO PEAXINC FROM AND EXCURSION STANDPOINT.

,REFEREt.CES . .

i 1. PETTUS' W. G.* " RESONANCE ABSORPTION IN U-CIE METAL AND OXIDE RODS'"-

g EAV-1244*.19C2.

2. HELLSTRAND' E.'. ET AL' "THE TEMPERATURE COEFFICIENT ,0F THE RESONANCE INTEGRAL FOR URANIUM METAL AND OX1DE'" NS AND EB' 497* 1960.

I

3. SPAND*-A. H.' " ANALYSIS OF DOPPLER-LIMITED EXCURSIONS IN A WATER-

{'

MODERATED OXIDE CORE'" NS AND El9'.172' 1964.

4. " MULTI-RECION REACTOR LATTICE STUDIES MICROSCOPIC LATTICE P f

IN SIN 3LE AND MULT1-REGION CORES'" WCAP-454' JUNE 1961.

• a l

?

II. CORE SPRAY INFORMATION ,

. l ,

T): FCLLCWING INFORMATION SHOULD ANSVER QUESTIONS RAISED REGARD

~

' . _SPCLY. AH1_ElllLDit? EDU AY - ~~...u.~. __.._.

.aa _ a _, .. _.,u._.a _ _ _ . , . _ _ . - , _ . , . . . . _. _ , . , . . _ _ . . , _ . .a _ _ ~ , _

~

THE E:. CLOSURE PRESSURE PEAX.GIVEN IN FIGuRT 3 0F THE SCnMITTAL -

", . *. .,1... .

. [ T-CHANCE !!O. 8 - TS DETERMII ED BY_THE TOTAL' ENERGY RELEASED It! THE 15-SECOND ELCVDOWN PERIOD.AND IS.NOT LIMITED EECAUSE OF CCRE SPT.AY.-

1

2. NEED FOR THE CORE SPTAY'TO COUNTERACT THE'HYPOTHETICAb METAL-VATER '

l l

P.EACTION DCEE NOT EEGIN'UNTIL 50 TO 100 SECONDS.AFTER THE ELOUDOW::' .

AC ILLI STRATED IN FIGURE 1 0F THE SUBMITTAL. ,

3. CORE SPPAY VALVE ACTUATION TAKES PLACE AT 200 PSI REACT 0Tt PRESSURE -

VMEN WATER LEVEL IS SIMULT ANEOUSLY LOV.' . CORE SPT.AY FLOW 'CT' AOUALLY INCREASES OVER THE NEXT 3 TO. 4 SECONDS AS THE BLOWD0VN QUICXLY REDUCEC

, . VESSEL PRESESRE AND PERMITS FULLL CORE SPRAY FLOW CORRESPONDI::G TO

. 'THE ENCLOSURE PRESSURE. THESE FEV SECONDS '0F PARTI AL FLOV ARE . y i

> INCONSEQUENTIAL. ,SEE TABLE.11.

t

., . 4. .AFTEP. SEVERAL MINUTES - REDUCED TO 5 MINUTES - THE CONTAINMENT-SPRAY COMES ON-IN PARALLEL ViTH THE CORE SPRAY. CORE SPRAY DRCPS TO APPROXIMATELY 91.5 PERCENT'0F ITS SINGLE FLCV VALUE. SEE TAELE 11.

5. AS Et:CLCSURE PRESSLRE. I DROPS TO ATMOSPHERIC LEVEL CVER THE ENSUING II MINUTES AND HOURS' THE CORE SPRAY IN PARALLEL FLOV INCREACES TO THE- ,;

INITIAL CORE SPRAY RATE.

TAELE 11 - BIG ROCK PCINT - CORE AND ENCLOSUhE SPRAY PERFORMANCE.

SPRAY N0ZZLE FLOV - GPM CONTAINMENT SPRAY SPRAY N0ZZLE FLOW - GPM k DISCHARGE PRESSURE CORE SPRAY CORE SPRAY- . CONTAINMENT SPRAY i -

VHIN PARALLEL VHEN PARALLEL.

PSIA ALONE

'. 15 400 363 352

s j 7

, 30 373 345. 323' 50 338 316 280 )

100 235 220' .170 a ,

i 150' 80 .70 48 I

l

. 165 0 0. O L . _ _ u _ . . _ . -

di . . -. . ';

'7 ". ~ II M Fl.*M: 20C: PSI C?c-~) SPEAY" f.CTUATICM - SEC-e 3.5 .

'3.2 -

2.8 1.9

.0.9 t

0.7 . .

FHSR A!;D TECHNICAL SPECIFICATICS D ATA - AFE CORRECT A!!D CONSISTENT. - FLO' S CITED CCERESPOND TO 00!:DITIONS WHEN SPRAY N0ZZLE DIFCHARGE PRESEU?.ES ARE e

• AT ATMOSPHERIC LEVEL. #

r THE CONTAINMENT PRESSURE TP.A:SIENT FOLLOUII:0 THE MCA HAS SEEN RE-EVALUATED FOR THE CASE WHERE BOTH THE. CORE AND BUILDINC' SPRAYS' ARE INCPERATIVE. THE CALCULATIONS SHOV NO CHAT:3E II: THE, PRESSURE TU.:SIE::T -[

URVE CUT TO ABOUT 20 SEC. THE!: THERE IS A SLOV RISE IN PRESSURE TO A ,

.,0' SECONDARY PEAK OF AEOUT 43. PSI A AT APOUT: 20'000 SEC. - THIS CA' CULA- [

TIC: TOCK'INTO ACCOUNT THE FACTORS NOTED I'if THE FHSR AND'.IN 035 RECEt:T F CHA!GE REQUEST SUBMITTAL PLUS A NEW SET OF CONTAINMENT VESSEL HEAT DISSIPATION COEFFICIENTS. THE NEk' SET OF. HEAT DISSIPATION COEFTICIENTS i

4 WERE DERIVED FROM EXPERIENCE GAINED HEATING BIG ROCK POINT CCNTAlt:"i i

) VESSEL WHERE A HEATING BOILER THREE TIMES THE CALCULATED IZE WAS- l NECESSARY' 70 PROVIDE PROPER HEATING.

/

R. L. HAUETER' ,

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Jackson, Michigan tra. mEuo, (R. L. Eaueter) 57 ORIG CC. OTHER.

10 1 2 15 era. repro & iced O CONCuanENCE O DATE AN$WERED W. Dean ACTION NECESSARY NO ACDON NECESSARY O COMMENT O SYi CLAS$1Fs POST OFFICE FRE CODE, I

U ato. No.

DATE RECElvfD By DATE DESCRIPDON (Most S. Undo"M REFERRED TO WX submitting addtl. info as requesW daring recent telecon regsrding the _g g,3 details of the accident analyses which wA - POR ACTICS supported their recent request for 04 CLOSURES.

Change h6 to the Tech. Specs of License ,

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< m -6...... , y , ,,,

DO iiOT REVOVE aExAars. nau moce utst.rtbation:

4 1-femal file sy. /176

. + 1-empe1. / tile ey. 2.oc cont up to Boyd earlier

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u. s. AtowC eseRoy co-sso" MAIL CONTROL FORM roRu AeC 1840)32es

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