ML20062E690

Transmits Calculational Results & Data Related to Staff'S Review of Odyn Transient Model.Info Incl Calculations Performed to Quanitfy Effects of Stuck Rod on Scram Reactivity & Series of Figures as Delta K Versus % Voids

ML20062E690
Person / Time
Site:	Peach Bottom
Issue date:	10/17/1978
From:	Cook K GENERAL ELECTRIC CO.
To:	Odar F Office of Nuclear Reactor Regulation
Shared Package
ML20062E688	List: ML20062E685 ML20062E690 ML20062E692
References
781026, MFN-399-78, NUDOCS 7812110274
Download: ML20062E690 (27)

Text

- ._ __

NUCLEAR ENERGY GEN ER AL h ELECTRIC PROJECTS DIVISION GENERAL ELECTRIC CC'MPANY,175 CURTNER AVE., SAN JCSE. CAUFORNIA 95125 MFN-399-78 MC 682, (408) 925-5003 October 26, 1978 U. S. Nuclear Regulatory Comission Division of Systems Safety Office of Nuclear Reactor Regulations Washington, D.C. 20555 Attention: Mr. Fuat Odar Gentlemen:

SUBJECT:

TRANSMITTAL OF REQUESTED DATA AND CALCULATIONAL RESULTS (ODYN)

The attachments to this letter provide a number of calculational results and data related to the staff's review of the CDYN transient model.

Attachment I provides the results of calculations perfomed to quantify the effects of a stuck rod on scram reactivity, which showed the one-dimensional model result to conservatively predict scram reactivity.

Attachment II provides a series of figures as ak versus % voids. These figures provide all of the ak data GE agreed, at the September 27-29, 1978 meeting with NRC/BNL, to supply to the staff.

[... ,

On October 17, 1978 the staff requested that GE provide additional data regarding the effects of exposure on the void reactivity in order to allow Brookhaven (BNL) to include this important effect in their audit calculations. The necessary data for BNL to normalize their calculations is included in Attachment III.

Specificall), the change in thermal absorption and thernal v - fission cross-section is given as a function of exposure for the controlled and uncontrolled states for 8x8 date and 7x7 bundle configurations. The data is supplied in tabular forms in tables 1 and 2, and in graphical l for n in figures 1 through 8. Also listed in tables 1 and 2 are the k '"

differences as a function of exposure.

Fast group infomation has not been supplied because the GE three-group structure is not the same as the BNL two-group structure, making the cross-section variations quite difficult to interpret. GE has done a i

few calculations and has found that if a two-croup approximation is used, a fairly good aporoximation to the change in k with void fraction can be obtained if the fast group exposure (E) and void (3) dependence is given by:

(a, E) = I (E)f (s) 7 gig 110 p.

. --_ y ,

t G E N E R A L (h) ELE CTRIC U.S. NRC Mr. Fuat Odar Page 2 October 25, 1978 and the thermal group parameters are taken frem tables 1 and 2. It should be pointed out that the above approximation worked reasonably well using GE fast group data. If BNL intends to use the same approx-imation, it is suggested that they check the k" variation with the ak, values given in tables 1 and 2.

The exposure differences will also influence the variation of the cross-section with moderator temperature. Attachment III also contains suggestions on how to change the moderator temperature dependence, as

(.

well as the void dependence.

8 It is GE's opinion that the consistent application of the exposure effects to the variation of thermal group constants will go a long way toward reducing the differences between the GE and BNL calculations of void reactivity. However, as has been demonstrated here, it is important to consider all aspects of a nuclear model, i.e., its ability to track critical eigenvalue and power distribution with exposure, before using it as a standard to judge other models.

Very truly yours, MJ, h K. W. Cook, Sr. Licensing Engineer Special Projects Licensing

(>

Q/

Safety & Licensing Operation KWC:bp/1017-18 Attachments cc: L. S. Gifford l

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ATTACHMENT I l

EFFECT OF A SINGLE STUCK R00 ON SCRAM REACTIVITY ..

Calculations have been carried out to quantify the effects of a single

~

stuck red on scram reactivity. The single stuck rod effect was eval-uated by performing 3-dimensional scram reactivity calculations in which alt-of the rod scram and in which the single most effective rod fails to ..~

scram. The reactor core consists of a 764 bundle, BWR/5 at end of cycle 1. The results are summarized in table I, along with the scram reactivity calculated by the 1-dimensional model. The stuck rod has a negligibly small effect on the scram reactivity, less than 0.3% over the important portion of the curve. Also, the difference between the 1-dimensional and 3-dimensional solutions is much larger than the stuck rod effect. The 1-dimensional scram reactivity is from 7% to 10% less than the 3-0 stuck red result. This difference is in the conservative f

direction. .

In summary, differences between the 1-dimensional and 3-dimensional scram reactivity results more than account for the stuck rod effects.

Therefore, the 1-dimensional model predicts scram reactivity in a conservative manner which more than ccmpensates for a single stuck control rod.

()

l l

KWC:bp/1019 10/25/78

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TABLE I

., SCRAM RIACTIVITY VS TIME

c. . .

TIME AFTER LCD 3-D SCRAM REACTIVITY 3-D SCRAM REACTIVITY 1-D START OF ROD INSERTION ALL RODS SCRAM 1 STUCK ROD SCRAM REACTIVITY MOTION FRACTION -(f/8) -(f/9) -(f/8) . _ , ,

O. O. O. O. O.

.1 .028 .0558 .0555 .

.0431

.2 .057 .1901 .1895' .1294 h'-

.4

.6

.114

.171

.4269

.6298

.4262

.6288 .

.3688

.5637 1

.8 .227 .9088 .9076 .7937 1.0 .281 1.2244 1.2226 1.1147 .

1.2 .336 1.6050 1.6026 1.4940 1.4 .391 2.0870 2.0839 1.9649 1.6 .445 2.8931 2.8882 2.6626 ,

1.8 .500 3.9483 3.9406 3.7180 2.0 .553 5.3652 5.3528 5.1053  ;

2.2 .607 7.3677 7.3465 7.0502 2.4 .660 10.9273 10.8880 10.0253 2.6 .713 16.2060 16.1340 15.2037 l 2.8 .767 23.7100 23.5740 22.5870 3.0 .820 33.4800 33.2420

• 32.3491

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ATTACHMENT II ak VERSUS % VOIDS DATA Attached are eight figures presenting the ak versus % voids for a BWR/4.

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i ATTACHMENT III

EXPOSURE AND VOID DEPENLENT CROSS-SECTIONS

- FOR PEACH BOTTOM-2 ANALYSIS e

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i SUGGESTED PROCEDURE FOR ACCOUNTING FOR EXPOSURE DEPENDENT EFFECTS ON VOID AND MODERATOR TDLPERATURE DEPENDENCE o

0F BNL 2-GROUP CROSS SECTIONS l

I VOID DEPENDE3CE CORRECTION A. Fast Group Cross Sections. X, i

t X'suic.4 's) X, H, E3 O X, (=<. , .<, E) = -

(

O X,_H., E= &

i. ;

where, 2-8.,L p((,E)= BNL f ast group cross section value at history void, f I

a(, , and exposure, 6 .

m X7(a(,Eso)= BNL fast group cross section value at instantaneous void, o( and zero exposure.

3. ThermalGroupCrossSections,k i ' gut CE X,(g, s, c) = x., c s., e)+ 4 x, cs -.< , o .

wh er e ,

t'~

X r(=',E) = BNL thermal group cross section at history, void, of , and exposure, E . .

G AN{t r N 'e E ) = GE A(thernal cross section) data (tabulated and plotted) e e sieme w-.

r. -wme< ..,e,,g aw M* ne m.

e-...-.w.-.-my.m e .w m

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II HODERATOR TDTERATURE DEPENDENCE CORRECTION

~

A. FastGroupCrossSection,Np su.

F F ( e' 6 h F

[g g 0) 2T-{g,5): Xl'ca,,e,c) a 7,,

r L

where, su.

{ N (d,52 a 0) = BNL moderster temperature cross section derivative OI. at zero exposure.

B. Ther:nal Group Cross Section, r f

9 X,(g aur 9 ,d, E )-

( a. , a, O = 4 Tr M cs,e..)

dT- / 2 x T-(' t, E = o ) arrm 3d e where, akt.

i O B(s do(

e=o) = BNL instantaneous thermal cross section derivative at zero exposure, l l L

i and w; ,

BNL moderator temperature cross section derivative at

~

(d,E*0)=

3T. zero exposure. {

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1,II CRECK ON VALIDITY Ol' CORRECTION Using the corrected cross scetion dependence on instantaneous voids, evaluate the infinite :nedium void coefficient at various  ;

exposures. '

Then conparu the corrected BNL values with the GE t.k. data ... .

(tabulated). If large discrepancies (significantly greater than 10::) are found, the su;;gested procedure for correcting BNL cross sections is invalid. A new correction procedure -

should be developed. Contact CE if the procedure proves to

(,' be invalid.

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V=0% V-40% V-70%

Exposure (MWD /T)

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~3  ! 0.0 -  ;

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s d f

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- 0.0 -

200 2.068x10' O.0 -2.767x10 -2

~ 6.757x10' O.0 -8.145x10 5,000 1.824x10 0.0 -2.771x10" -2

-2 7.683x10" 0.0 -9.277x10 10,000 2.748x10 0.0 -3.982x10" ~ -2

~

7.589x10 0.0 -9.026x10 2.877x10

~

0.0 -4.065x10 f 15,000 -2 I

-2 - 0.0 -

25,000 2.757x10 0.0 -3.797x10 l .

t

. l

. . TABLE 2  ;

8x8 FUEL 8D274 5Gd2 80 mil UNCONTROLLED CONTROLLED (V): A (V)* (V)- [g/407.)

A (V)* bg [CY 1 l

V=0% V=40% V=70%

Exposure V=0% V=40% V=70%

(WD/T) ,

1

~

~

0.0 -3.094x10" 4.564x10 0.0 -5.507x10 'I 200 3.289x10" ~

~

~

- 5,000 3.095x10

~

0.0 -2.765x10 ~4.146x10 0.0 -J.099x10

~ -3 2.868x10" 0.0 -2.485x10" 3.896x10 0.0 -5.527x10 0,000 +

~ -3 3.711x10" 0.0 4.819x10~3 15,000 2.740x10 0.0 -2.319x10 ~

-3 ~3 0.0 -5.248x10  :

25,000 2.532x10 0.0 -2.088x10 3.427x10" i

AV (V .,, b Fk(Y)- t 7- 4[y (V) ,

2 b7 (V) ~ 4 7s V=70% V=0% V=40 V=70%

V=0% V=40%

~ ~ ~3 2.840x10" 0.0 -2.689x10 4.594x10 0.0 -5.117x10 200 ~ ~

~

~

0.0 -2.244x10  ! 3.923x10 0.0 -4. 657x10 5,000 2.254x10

-3 -3 0.0 -3.489x10' 10,000 1.936x10" 0.0 -1.899x10 l 3.375x10

~ ~3

~

-1.550x10"  ! 2.954x10 0.0 -3. 531x10 3,000 1.649x10 0.0

~

~3 ~3 0.0 -2.002x10" 0.0 -1.034x10 2.164x10 25,000 1.165x10 f -- _ __

A k(V) - ((V)- ((4C4) g((V): kCr)- ((40'i.)

V=0% V=40% V=70%

V=0% V=40% V=70%

-2 -2

-2 0.0 -1.839x10" 5.779x10 0.0 -6.468x10 200 1.638x10 ~

~

~

0.0 -3.434x10

~

7.468x10 0.0 -a.820x10 5,000 2.350x10

-2 -2 -2 0.0 -a.123x10

-2 10,000 2.827x10 0.0 -3.879x10 7.637x10

-2

~

0.0 -3.931x10

~

! 7.506x10" 0.0 -8.529x10 15,000 2.923x10 ~ -2 0.0 -3.684x10

~

6.926x10 0.0 -7.000x10 25,000 2.301x10"

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