ML20002C866

Informs of Minor Changes in Two lead-in Bundles of Reload G Batch Due to Fuel R&D Programs.Changes Should Not Require Tech Specs Change.Local Power Distribution Maps for Bundles Encl

ML20002C866
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	07/09/1974
From:	Sewell R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	Oleary J US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8101120217
Download: ML20002C866 (7)

Text

o 7._,.

f

~

j, Consumers 4

C L

Power L @%;m Ei

(

.J6 Comp 2Ry

/~~

(,s

,n'

\\.

~

General Offices': 212 West Michigan Avenue, Jackson. Michigan 4920s. Area Code S17 788-0550 Nj/

July 9, 1974

.b

+

'/ O nmOG

^

N USAG Mr. John F. O' Leary, Director JUL D C-,Re: Docket 50-155 g,g gst O

License DPR-6 Directorate of Licensing Q

yj{

Big Rock Point US Atomic Energy Commission p

y

\\ DW Washington, DC 20545

/g/

Dear Mr. O' Leary:

I/lG\\

This letter is written to inform you of minor changes that have been made in the two lead-in bundles of the reload G batch at the Big Rock Point Plant. These changes are due to fuel research and development (R&)) programs that are being conducted at the Big Rock Poist Plant similar to those that have been conducted in almost all reload fuel batches in the past.

.r In order to perform fuel R&D, it is frequently necessary to move or change fuel rods within fuel bundles. A design objective of these fuel rod changes is to assure that the resulting peaking factors and power dis-tributions remain within previously analyzed envelopes.

In the case of the changes associated with the two G lead-in bundles. (G-01 and G-02), the previously analyzed envelopes had been slightly exceeded. The following vill describe our evaluation of these changes.

During the present refueling outage, three fuel rods were re-moved from the two G lead-in bundles as sumarized below:

Fuel Bundle Fuel Rods Withdrawn Fuel Rods Inserted G-01 One high-ductility One inert Zircaloy rod.

clad test rod.

G-02 Five short-cycle Three original fuel rods test rods.

(had been withdrawn after Cycle 11) and two inert Zircaloy rods.

The rod removed from Bundle G-01 is a test rod associated with a program to evaluate and develop a superior high-ductility cladding that may ulti-mately result in fever fuel failures by brittle fracture due to pellet clad interreaction. The five rods removed from G-02 are associated with variods tests to evaluate the effect of pellet process parameters on in-core pellet densification. Three of the fuel rods reinserted had been removed during the previous refueling outage that ended in May 197h.

F/oye6R/7

Mr. John' F. O' Leary 2

Docket'50-155, License DPR-6 Big Rock Point July 9,1974 The inert Zircaloy rods used fbr replacement are only to provide a hydraulic plug and to displace water during normal operation. The ECCS analysis performed to determine the effect of these changes on the fuel bundle assumed no credit for wetting of these rods as a heat sink during rod / channel vetting.

The local power distribution maps for the bundles after the present modification are shown in Figures 1 and 2 for G-01 and G-02, respectively. Figure 3, the local power distribution prior to modifica~

tion, is included fbr reference infbrmation.

For G-01, the local peaking factors in the vicinity of the inert rod increase 2% to 5% due to the absence of neutron absorber.

The maxi-mum local peaking factor is 1% greater than before modification; however, it is still 3% less than the maximum local peaking factor for a new G bundle (which is routinely used in thermal hydraulic analysis by Consumers Power Company).

For G-02, the local peaking factors in the vicinity of the inert rods increase 3% to 7%. The maximum local peaking factor is 2% greater than before the present modification, 5% greater than before the short-cycle test but only 1% greater than the maximum local peaking factor for a new G bundle.

The locations of the highest local peaking factors for the as-modified bundles are similar to those before modification. Use of these local peaking factors in preference to beginning-of-life local peaking factors should yield similar or less limiting results during thermal hydraulic analysis.

Bundle heatup analyses for the large break IDCA case were per-fbrmed on the as-modified bundles. The results are presented in Attach-ment 1.

It can be seen that, within the expected accuracy of such calcu-lations, the results are not appreciably different from those for a standard G bundle. The slight increase is believed to be almost entirely due to in-creased power density necessitated by power normalization assumptions and the decreased number of fueled rods.

The 8.6T kW/ft MAPLGR limit of the proposed Technical Specifi-cations dated June 28, 1974 should be more than sufficient to compensate for any increase due to the inert rods since the MAPLGR corresponding to the 2.1895 gross peaking factor used in the attached analysis would be 8.95 kW/ft.

In addition, the next cycle (Cycle 13) as presently planned at Big Rock Point will be loaded such that reload F fuel represents the limiting peak clad temperature from the ECCS standpoint.

It is anticipated that reload G fuel vill run at no more than about 78% of the 8.87 kW/ft proposed limit.

Based on the analysis summarized above, we have concluded that these two fuel bundles may continue to be used in the Big Rock Point

Mr. John F. O'L';ary 3

- Dockst-50-155, Licsnao DPR-6 1

Big Rock Point.

July 9.-1974 j

i Plant reactor. We have further concluded that the operating limits con-tained in the Technical Specifications (including the proposed change dated June 28,1974) are. conservative. In our opinion, the minor changes described above do not constitute a sufficient change in this fuel to re-quire a change _in the Technical Specifications.

Yours very truly, RBS/ map Ralph B. Sewell Nuclear Licensing Administrator CC: JGKeppler, USAEC Peter W. Steketee. Esq 4

9

YIGURE 1 - LEAD ASSEMBLY G01 -- LOCAL POWER DISTRIBUTION AT 8000 MWD /MT, 25% V0ID CONTENT (After Modification)

C0 1.072 0.979i 1.133 1.090 1.081 1.098 1.142 0.983 1.074 C0 1

1.072 1.104 0.966 1.124 1.070i 1.068[ 1.104 1.148' O.974 ' l.108 1.073 il e

I I

0.977 0.965 1.033 0.902 0.845 ) 0.855[

Zirc 0.939 1.046 0.968 0.978 i

e i;

y 1

9 Y

I 1.129 1.119 0.898 1.077 0.959 '

O.953[ 1.004 1.108 0.906 1.122 1.130 1.083 1.057 0.831 0.947 0.824 0.822I 0.833 0.956 0.835 1.058 1.082 I

t, P

ll li 1.069 1.039 0.813 0.918 0.81 3 ( Zirc ! 0.815 0.921 0.814 1.039 1.068 r

9 0.81800.812! 0.819 0.945 0.831 1.056 1.082 l.083 1.057 0.831 0.945 I

t.

I I

i y.119 0.897 1.072 0.944il 0.917] 0.944 1.071 0.896 1.118 1.129 1

1.130 5

0.978 0.965, 1.032 0.897 0.831! 0.813! 0.8'30 0.896 1.031 0.963 0.977

[

t i

t 1.073 1.105 0.965 1.119 1.057[ 1.039[ 1.056 1.118 0.963 1.103 1.071

{

(

CO 1.073 0.978 - 1.130 1.082 1.068,) 1.082 1.129 0.977

, 1.071 CO

\\

y K = 1.1437 E = 8000 MWD /MT

..o

.j

. J ',

FIGURE 2 - LOCAL POWER DISTRIBUT10tl - LEAD ASSEMBLY G02 AFTER MODIFICATION, 25% VOID C0ilTEllT CO 1.070 0.980 i 1.144 1.116 1.121 1.115 1.142 0.979 1.068 C0 7-1.067 1.101 0.967 1.137 1.114l Zirc ' l.113 1.136 0.966 1.100 1.065~

h:

3 i

i 0.973 0.961 1.033 0.908 0.862!

0.864l 0.862 0.908 1.032 0.960 0.971 i

i I

s' s

e!

i<

1.123 1.114 0.895 1.078 0.961.[ 0.941[;

0.961 1.077 0.895 1.113 1.122 t-9 fe f

1.076 1.051 0.827 0.943 0.820[l 0.81 4 0.820 0.943 0.828 1.051 1.076 i

i; i:

1.062 1.033 0.809 0.913 0.809[ ZircI 0.810 0.916 0.810 1.035 1.063 I

t i

1.076 1.051 0.826 0.940 0.816 ! 0.811 I 0.821 0.949 0.832 1.056 1.079

?'

l s

t,

[

1.123 1.112 0.892 1.068 0.946I. 0.926j- 0.965 1.100 0.909 1.124 1.129 L

L l

r 0

l 0.972 0.960 ;1.027 0.895 0.834[ 0.827 0.867 0.955 1.069 0.976 0.980 F

i I

1.067 1.099 0.961 1.118 1.063[ 1.061E 1.120 Zirc 1.017 1.123 1.077 f

y _.

L C0 1.068 0.975 1.129 1.088.

1.086 : 1.120 1.189 1.009 1.087 CO 0

l K.

= 1.1434 Y

= 8000 MWD /MT

I l

LEAD ASSEMBLY G01 -- LOCAL POWER DISTRIBUTIO!1 FIGURE 3 AT 80"] MWD /MT, 25% VOID CONTENT (Prior to Modification) o Cobal t 35 1.078

.983 1 1.T37 1.089 1.075 gm/ft i.

l' l.110

.969 1.126 1.063!'l.045 il j

i-Out 1.037

.901

.834

.816l

.834 I

t-rl V

1.084

.954;,

.926 o

i

.825

.816I i

I i!

I n

i Zirc i i

I;

).

i:

OCTANT SYMMETRY f:

i i

I "ll

[l i

l' 4

l l

y a

f I

t i

I L

):

(:

.=.._:

l

.i 0

t K. = 1.1428 E = 8000 MND/MT e

4

i i

s w.

ATTACHMENT 1 LARGE BREAK LOCA PEAK CLAD TEMPERATURES G01 G02 2

1.

Using h

= 1000 Btu /hr-ft ap

. a.

Original assembly 2286 F 2286 F

b. - With five fresh test rods ' fueled) 2285

. c.

With two zircaloy replacer.nt rods 2299 d.

With one zircaloy replacement rods 2293 2.

Using Exxon Nuclear's approved BWR densification model at 8 GWD/T:

a.

Original assembly 2297 2297 b.

With five fresh test rods (fueled) 2297 B

c.

With two zircaloy replacement rods 2337 4

d.

With one zircaloy replacement rod 2317 Notes:

A.

lieets 2300 I AC limit at axial

• radial = 2.18 (fr=1.44 0 fa=1.51)

B.

Meets 2300 IAC limit at axial

• radial = 2.17 (fr=1.43 @ fa=1.51)

All' analyses are based on an axial times ra?ial power factor of 2.1895.

The increase in temperature with the introduction of the replacement rods is due to the increased power density necessitated by the decreased number of fueled rods.

a 4

AEC DISTRI:

70! FOR PART 50 DOCKET PATERIA' 6276 (TD100RARY F0PJ1)

CONTROL NO:

/9,/,f/

O FILE:

FRCM:

DATE OF DOC lDATE REC'D LTR TWX RPT OTHER Connumers Power Company J::ckron, Mich. 49201 Mr. R.B. Sewell 7=9 74 7-11-74 X

T02 ORIG CC OTHER SENT AEC PDR M

J.F. O'Learv 1 signed CLASS UNCLASS PROP INFO INPUT NO CYS REC'D DOCKET NO:

XXX 40 50-155 DESCRIP2 ION:

~

ENCLOSURES:

Ltr cdv of changes in the lead-in bundles of the retrad G batch......and and adv that they feel th t this d ange should not require a change to 7qTmr-r qq-,/

-- - v \\ *

' s t:ch specs.........

v~~

no DON 0ym-1 la. v w PLANT NAME:

Big Rock Point JB ~

~'

FOR ACTION /I:TORMATION I'[IE'74 BUTLER (L)

SCDJENCER(L)

/ZIDiANN(L)

REGAU(E)

U/ Copics W/ Copies W/7 Copies U/ Copies CLARK (L)

STOLZ(L)

DICKEn(E)

LEAR (L)

U/ Copies U/ Copies W/ Copies U/ Copies

• ~2I7 F5(r)

P."Jm(L)

V!Er._=(L)

W/ Copics U/ Copiec U/ Copies w/ copies D11EL(L)

PURPLE (L)

YOUNGELOOD(E)

W/ Copics U/ Copics W/ Copies W/ Copies

~

INTE?J'AL DISTRTEUTIOM r

_y.

j PIG FI,1X TECH REVIEW DE'; TON LIC ASST A/T IND F AhC PDR HENDRIE GkIMES BRAI'IE.

/0GO, ROOM P-506A SCHROEDEi GALE 4ILL

/ DIGGS (L)

SALTZMAN MUMTZING/STAPP MACCARY KASTMER GEARIN (L)

E. HUR'T CASE D1IGHT BALLARD GOULEQUPl1E (L) ptagg GIR4BUSSO PAULICKI SPANGLER KREUTZER (E)

MCDO:IALD BOYD SHA0 LEE (L)

CHAPMAN MOORE (L)(INR)

STELLO ENVIR_0 MA1GRET (L)

DUBE v/ input DEYOUNG(L)(E;R)

HOUSTON MULLER REED (E)

E. COUPE SE0VHOLT (L)

NOVAK DICKER SERVICE (L)

/COLLER(L)

ROSS DiICHTON SHEPPARD (L)

D. THOMPSON (2)

P COLLINS IPPOLITO YOUNGELOOD SLATER (E)

KLECKER DENISE TEDESCO REGAN SMITH (L)

EISENHUT

/ REG OPR LONC PROJECT LDR TEETS (L)

FILE & nEGIO::(3)

LAINAS WILLIAMS (E)

MORRIS BENAROYA HARLESS WILSON (L)

STEELE VOIRIER

/4 EXTE5'l:AL DISTRTFJTION 1-PDR-CAN/LA/N

- LCCAL PDR ' Charlevoix._ Ifich.

- TIC (ABERNATnY)

(1)(2)(10)-UATIONAL LAB'S l - KSIC(EUCEANAN) 1-ASLEP(E/;,' Eld;,Rm 529) 1-LIBRARI A';

1 - ASLB l-W. PE:;NINGTO:?, Rm E-201 CT BROOKEAVEN NAT. L C 3 - P.

R., DAVIS (AEROJET NUCLEAR) 1-CONSULTANT' S 1-AGMED(Ruth Gusst4 A6 - CYS ACRS wwusiMG Sent to Diggs NEW ARK /SLU"C/AGBAEIAN Di-B-12 7. CT.

1-16-74 1-GERALD ULRIRSCN...ORUL l-LD.. MULLER..F-30 ~

1-B & M SWINESROAD,

,4-401 Gg y k

N