ML20126E285

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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)
v • d • e


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

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MR. ROBERI L. HAUETER ED FROM CONSUMERS POWER COMPANY

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MAY3 1966 > 11 i

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DOCKET 155 4

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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 "UI VERY NATURE OF THE CkLCULATIONS AND THE NECESSARY CONCOMITANT Q L__

_U.MPTIONS'. THESE CHANGES CANNOT BE REGARDED AS SIGNIFICA.NT. --

ASS r

=..-- - -. - -. - -, - - -. - ' -

  • 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 i.

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

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  • 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 -

2'200 2'200 LB E.

UD2 EXCEEDING 360 6

CAL /GM-CLAD RUPTURE' LB 529 370

?

9.

U02 IN RUPTURED FUEL g

RODS

  • LB l*550 l*240 1

10.

CHEMICAL ENERGY FROM NOT NOT METAL-VATER REACTION t

MV-SEC C ALCL'L ATED

_ CALCULATED GAS TROM METAL-VATER 11.

REACTION' SCF H2 110T CALCULATED NOT CALCULATED 1-l t

(')

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

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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 i

MILTING - LB l'420 2'4GO 450 510

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UO2 EXCEEDING 360 I

CAL /GM-CLAD RUPTURE' LB 450 500 NEGLIGIBLr NEGLIGIE i

1 S.

UO2 IN RUPTURED FUEL ROD 5' LB l'500 3'160 NEGLIGIELE NEGLIGIEE i

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10.

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

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W ATE' REACTIO..

SCF H2' 6SD I'SEO

. 160 390

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

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--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

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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

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THE L ATEJT ANALYTICAL TOOLS ' AND METHODS VER~ EMPLCYED THROUGHCUT-THE Pr.ESENT ANALYSES. THE CHANGES AND THEIR EFFECTS WILL BE DISCUSSED.

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l 1.

TO INCOTsPCR ATE REACTOR SPATI AL EFFECTS I';TO THE DOPPLER FEEDS ACK 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 f

CALCULATION REPRESENTS THE AVERAGE REACTOR CONDITION.

4 THIS' INCREMENT OF POWER' EXPRESSED AS A FUEL TEMPERATURE CHANCE' IS

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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

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

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ElGENVALUE CHANGE RESULh11 G Th05 L A Ui IFORMLY.

TMIS CALCULATION TO T DISTRIBUTED TEr.PERATURE It1CREMENT'PF0VIDES AN ACCURATE ESTIP. ATE OF.THE DCFPLER EEICHTIN:; FACTOR APPF10PRIATE FCR THE NEXT KIHETICS CALCULAT10::AL

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

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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.,

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

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

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

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

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r EXTENDED TIME. PERIOD.

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

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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 THAN THAT RESULTING TECX USE OF PETTUS DATE -

I'- AND 13 PERCENT LESS i

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

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

PRECISELY BY THIS FORM IN BOTH DIFFERENTIAL MEASUREMENTE - 1*2'3 - AND i

GROSS CORE DYNAMIC MEASUREMENTS - 4.

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

IFTECTS' ARE SIMILAR IN DOPPLER COEFFICIENT. THE 13 PERCENT DIFF 5

IN DOPPLER COEFFICIENTS USED IN THE CALCULATICNS IN REFERENC l'

RELOAD AND STANDARD FUEL VAS CALCULATIONAL AND NOT A PHYSIC i

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

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. 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-l RESULTA"7 VALUE FOR BOTH FUEL TYPES IS.t:EG ATIVE l'.1 TIMES 10' TOI HE T

MIKUS 5 DELTA K OVER.K PER DEGREE ~F AND{IS.QUCTED11N.CHAN2E NO.8..

}

4.

THE INITI AL POWER.IS ASSUMEC TO BE 10 TO THE MINUS 6 0FJ RATED IN THE HOT STAT:DBY CONDITION. ' THE PREVIOUS : AN ALYSISl ASSUMED. '10' TO. THE t

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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. CORE' REACTIVITY AT WHICH A PROMPT CRITICAL S

i -

A*CIDENT COULD. 0CCUR WITH A 0.046 DELT A X ACCIDENT.' THIS REACTIVITY IS APPROXIMATELY 0.961' AT WHICH CORE MULTIPLICATICH IS 25.'6.

-INCREAS-It;ITI AL POWEP KESULTS 'IN A SLIGHT REDUCTICN IN ACCIDENT EEVERITY. '

IU" REACTIVITY IS ADDED ON THE' ACTUAL l WORTH-DISTANCE RELATIONSHIP 5.

"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.

THE LOCAL PEAKING HAS.BEEN INCREASED TO REFLECT THE SPECIFIC P C.

OF THE SMALL CORNER FUEL RODS.. THESE RODS. HAVE THE' HOTTEST c LO PEAXINC FROM AND EXCURSION STANDPOINT.

,REFEREt.CES.

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

i 1.

EAV-1244*.19C2.

g HELLSTRAND' E.'. ET AL' "THE TEMPERATURE COEFFICIENT,0F THE RESONANCE 2.

INTEGRAL FOR URANIUM METAL AND OX1DE'" NS AND EB' 497* 1960.

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

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

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

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

a l

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II.

CORE SPRAY INFORMATION FCLLCWING INFORMATION SHOULD ANSVER QUESTIONS RAISED REGARD l

T):

. _SPCLY. AH1_ElllLDit? EDU AY -

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

",. *. 1.

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[ 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.

. 4.

.AFTEP. SEVERAL MINUTES - REDUCED TO 5 MINUTES - THE CONTAINMENT-t 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.

AS Et:CLCSURE PRESSLRE. DROPS TO ATMOSPHERIC LEVEL CVER THE ENSUING II I

5.

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

VHEN PARALLEL.

PSIA ALONE VHIN PARALLEL 15 400 363 352

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7 30 373 345.

323' 50 338 316 280

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100 235 220'

.170 a

i 150' 80

.70 48 I

l 165 0

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20C: PSI C?c-~) SPEAY"

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f.CTUATICM - SEC-e 3.5

'3.2 2.8 1.9

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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-

[

TOCK'INTO ACCOUNT THE FACTORS NOTED I'if THE FHSR AND'.IN 035 RECEt:T TIC:

F CHA!GE REQUEST SUBMITTAL PLUS A NEW SET OF CONTAINMENT VESSEL HEAT DISSIPATION COEFFICIENTS. THE NEk' SET OF. HEAT DISSIPATION COEFTICIENTS i

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

4 i

)

VESSEL WHERE A HEATING BOILER THREE TIMES THE CALCULATED IZE WAS-i l

NECESSARY' 70 PROVIDE PROPER HEATING.

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DESCRIPDON (Most S. Undo"M REFERRED TO DATE RECElvfD By DATE 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 a

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