ML20064A639

From kanterella
Jump to navigation Jump to search
Startup Test Rept Unit 2 Cycle 2
ML20064A639
Person / Time
Site: Braidwood 
Issue date: 06/30/1990
From: Hunsader S, Thomasen J, Wiegand C
COMMONWEALTH EDISON CO.
To: Davis A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NUDOCS 9009170084
Download: ML20064A639 (39)
v • d • e


Text

r

'o Q

b.

((

g h b3
.g

' a#-

'! Commonwealth Edisonl ig A.

',L L1400 Opus PI:ce.

Agjg Downm mow, Mnois 60515,

' K0m dy}q '

i I

l!9"-

$i

> D[,p

. August.16', 19901

' g%

g;d jg g>

$kk ' :- l [

' g' oEL pf@p['#

Q 4:

J

- fTL(,tif,

'1 fi L~m k ' 9 w Regiona1> Administrator-3 li.

! Mr:.' Al Bert.Davisi Q

(U.S. Nuclear Regulatory Commission

% g" 6 tRegion IIIf 799 Roosevelt Road

  • i 7 Glen'Ellyn. IL.60137 1

. m-

  1. j Braidwood Station Unit 2 m

Subject:

" [N

~

. Cycle 2'Startup Report s

JiRC Docket No. 50-457 1

w%

?t.

yt;_ )

4 e

4i

DearJ r.-Davis:

M j

'l Section' 6.9.1 of the Braidwood Technical Specification states,:in-J

.' : addition to the applicable reporting requirements of Title 10L Code'of Federal; s

Regulations,'the<following reports shall be submitted to the Regional.

. g{ s j iAdministrator of-the:NRC'. Regional Office unless otherwise noted:

'I F

6.9.1.l' A summary report of plant scartup and. power escalation.

testing shall3be submitted following:

(1) receipt of an Operation License,:(2)- amendment to the 11 cense-involving a planned Lincrease in' power level. (3) installation of fuel that has a different design or;

~ '

~

has been manufactured by a different fuel supplier, and (4) _

~n modificationsithat may have;significantly altered the nuclear,-.

. thermal,,or hydraulic performance of the plant.

4

,y

,w'c' 6;9.1.2.

The Startup Report shall-address-eafh of the tests.

s,'

identified'in the Final Safety. Analysis' Report FSAR~and-:shall. include ',

y a= description'of the measured. values of the' operating-conditions?or?

l' zl

/P characteristics obtained during the test program and;a comparison of-

,8 s-these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory

%e > 1

-operation shall also be described. Any additional specific details required in license conditions based on other. commitments shall'be

tr.cluded'in this report; N, s.

M.

6.9.1.3...Startup Reports shall be submitted within:

(1) 90 days following completion of the Startup Test Program, (2) 90 days following resumption or commencement-of commercial power operation,

~

or (3) 9 months following initial criticality, whichever is M

earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startup Test Program, and resumotion of commencement of commercial operation) supplementary reports-shall be submitted at least every 3 months until all three events have been completed.

O

[

AU8 2 019110 a 0 e;t n 4

c.-

y 0

. 'a.

m:

' ~ '

N 91

' i1 o

m o..

o

q p[h:

j;[my

~

+

1 4

s

.g s

y ;,;p y,

a 9,'g;

,lMr.LA.'Bert~ Davis.

-'2:-

- August 16,' 1990:

li,

In accordance with Specification 6.9.1.1(3) and:6.9.1.3(2), enclosed g; [v1.N', 'is/the Braidwood Uni.t 2, Cycle 2;Startup. Report..

m-

..4, Please address any questions;r'egardingLth,is submittal'to this office.

< Respectful.ly)

U C'

K S.C. Hunsader

_ Nuclear Licensing: Administrator l

cc:; NRC'Do'cument. Control-Desk l

S. Sands, NRR Resident ' Inspector :- Braidwood H.5Shafer, RIII a

i

." 1mw/ID179-I t

1 l

L,

.j

.Li s

y.

l+

l '9.

,i-

.2

.,j li

.i j

a.

y r

(\\

ts'

.j

!.),

s 3n t

2.

-f

=,

e f'

3 (l.(g a, _ --

., {le '-

n u

s,3..,,

n,

.o 1,

y;..

gy

., s --

u E

I.

, o ;-

5 Ik',$

h,'[ ' '-

i[

8 s

i.. 33

'U j[,

9.;=

n 4

i S,

,,1 i

j af.

f.;g, 4

.1.

3 L

gj.

. e-

r-
j;

' ii

,i

, e );

,8

\\ _

\\

1

. f),

+

-T COW 40NWEALTH EDISON COMPANY-E BRAIr,100D GENERATING STATION-

,gr o-f,

+

M;<

DOCKET NO. 50-457 c

' LICENSE NO._NPF-7f-t v?.

s t

, UNIT-2 CYCLE.2 e

t L

STARn!P TEST REPORT vi JUNE 1990 a

PREPARED BYt.

JOHN.P. THOMASEN APPROVED BY ig ; '

CHRIS M. WIEGAND

'n s

(p et,,

.. g..

e k'/

s J2:

'l 4

' f.'.

f i;

)

I i

b; s -

-o, s

gt

  1. ;;g sl*

5 l[ % s i - f,'

TABLE OF CCalTENTS o

im

~

Y SECTICEI PAGE 4

- TABLE'Or. CONTENTS; 1_-

i LIST-OF-ILLUSTRATIONS 2

- LIST OF TABLES, 3

.1.0, INTR'ODUCTION, 4

~'

2.0 CORE-CONFIGURATION-5

(-. -

2.1 UNIT 1, CYCLE 2 CORE INFORMATION' 5

,q:n 2.2 UNIT 2+ CYCLE 2 CORE INFORMATION 6

'3.0 CONTROL ROD DRIVE SYSTEM 15 3

'-3,1: CONTROL ROD-DRIVE SYSTEM' CHECKOUT 15 4

3.2-ROD DROP TIME MEASUREMENTS-17-

-4.0 INITIAL-CRITICALITY 17 5.0 ZERO POWER PHYSICS TESTING 18 5.1 BORCH ENDPOINT MEASUREMENTS 19'

5.2 ISUTHERMAL/ MODERATOR ~ TEMPERATURE 20 COEFFICIENT MEASUREMENTS

. 5.3 ROD AND BORON WORTH MEASUREMENTS 21 6.0 AT POWER PHYSICS TESTING 25 7.0:REACTIVITZ ANOMALY / BORON FOLLOW 32

8.0 CONCLUSION

AND

SUMMARY

-34 7

9.0 REFERENCES

37 1

43(072390)/2 ZD79G m

. l.

,,, w _

. 'e. -i G gqp.

Tpq >,

f

)

o..

%,;..p r

t

~

a

< ' lt, y

llgs':3-c;-

3 l'

LIST OF ILLUSTRATINS I

5:

l

,e

I W

'a" n.

r FIGURE NO.

DESCRIPTIN

PAGE 4

' l i,, '. -. I f."'

i.s W g 2.1-LOCATION OF SOURCES AND BURNABLE =

,9.

l c' ABSORBER RODS IN BRAIDWOOD 2 CYCLE 2 a

t a

r

~

L!! go.

-2 2.2

. LOCATION:OF FRESH IFBA' RODS-IN ASSEMBLY

'.10 lg

,.)

1-2.3 BRAIDWOOD. UNIT 2' CYCLE.2 REGION. NUMBERS

'13 AND ASSEMBLY ID'S, i

l"

+

,3 l?

2.4' BRAIDWOOD UNIT 2 CYCLE 2 CORE INSERT MAP:

,14

P l :2.;

lu A -m.

6'. 11 STARTUPLPHYSICS TESTING POWER HISTORY 31 h.

W. ! !

p.

7.1

.BRAIDWOOD 2 CYCLE 2 BORON FOLLON DATAT 33.

9 t

> r..,

l-,

J a

+.

e I,

I l

i i l..l

.[

+

'I i

l.

f

', s i

I' l

t l

r p;

s 1:

a

(

i l-w i

I =.

t I

2 43(071790)/3 ZD79G t

6 t

op

..y jyl['0, y**

'.,* [

.
l

~

  • [j qh.

-f g.:

c,

+ i

,,'..1v.

J n ; -!

4 y

+

ya

' a; c a '.,

ht i $

-k

,4 LIST OF TABLES 5

TABLE NO.

DESCRIPTICM EAGE j

g, 1-

-;q

,g

.'t y-5 2.1-BRAIDWOOD UNIT 2 CYCLE 1 CORE REGION

' DESCRIPTION I

i 2'.23 BRAIDWOOD UNIT 2 CYCLE 2 CORE REGION 8

Ao DESCRIPTION da ' n_

n

' HOT. FULL FLOW ROD DROP TIMES 16 _

>a

-. 3.1 0.

UNIT 2-CYCLE 2

.)

5 '.1 BRAIDWOOD UrIT'2. CYCLE 2. BORON ENDPOINT.

19-

'DATAL 2

5.2 ISOTHERMAL / MODERATOR TEMPERA'IURE 20-COEFFICIENT MEASUREMENTS

.a ~

RO'D EXCHANGE MEASUREMENTS.

24 5.3 i

l 6.1

> Fay MEASUREMENTS DURING' POWER ASCENSION 28-T 29 6.2 FLUK MAP CHARACTERISTICS'

.' 6. 3 FLUX-ilAP RESULTS

-: 30

-PHYSICS TESTING

SUMMARY

35

'hi 8.1-

. 8.' 2 TEST CRITERIA-36:

j

  • i s

?

J 4

i)-

4 3

q.

43(071790)/4 ZD79G m

.I

,,.... ~.. _. _.....,.................,..

' QGn 7

v,9 i

o if'%

lsl[

',[

Ie

' 1.0 INTRODUCTICM R

Braidwood Unit 2:.ycle'1: began commercial; operation on October l,,

17,~1988' and completad it's operating cycle on March 16,'1990.

m-The Cycle,1 final' core average burnup was 17,895 MWD /MTU and the

' unit lost'fu11' power capability on December. 25, 1989_at a core:

average burnup of' 15,701 MWD /MTU.

y i

A full core. offload.was conducted from March.30,.1990 through.

LApril-1,'1990. : Irradiated fuel, inspections were performed using an underwater camera and video equipment. No significant-l'J

' defects were found.. Cycle-2-core load was performed beginning April 11,11990 and ending on' April-15, 1990. 'The core was

1oaded'according to the core loading pattern provided by I

Commonwealth Edison = Company-Nuclear Fuel' Services (NFS) t,'

Department.

EUnit 2. Cycle 2. initial' criticality was: achieved on May 25, 1990

,and Zero Power Physics testing was performed from May125, 1990 s

through May 26, 1990. Mode 1 (> 5% RTP) was entered on May 27, 1990 at approximately 1120 hours0.013 days <br />0.311 hours <br />0.00185 weeks <br />4.2616e-4 months <br />. At-Power Physics. Testing was

. conducted-from June 1, 1990 through July =2, 1990.

4 43(072390)/5 g

ZD790 I

w y.

3 l, /

/.

ui 6

[b[N '

l,y,

,l

(;; .g+'. M s

r u

S.h\\d,g-j'8 '

1 a :: r

,,.a s 1

Qik)h.:-- \\

'^\\*

%+

l I." $;'

'2.0 CORE CCRIFIGURATICRI y/.

c 3

r i

m.

^ 7). ) < p',,

<ji

m 2.1 UNIT 2 CYct.E 1 CORE INFORMATICM,

,r

'!. I '

.m Oi Y

Braidwood Unit ~2 Cycle 1. began commercial operation-on October

-17,;1988.

Table 2.1 below details theLcoreiregion information M,'-#

0V 1

.for=this cycle of operation..

l w - ',

y3

..)

t T

1 l, I:

n

C yw

- y.,

TABLE 2.1 i

ll A. #;":

\\g BRAIDWOOD UNIT 2 CYCLE'1 r.

...m l :li,

i CORE REGION DESCRIPTION l

1:

. M

- j'h,,

3 7

' ' in k

33 1

l'

,'.i.,

r i

yj. '

Realon~1 Realon'2 Realon 3' Hjmber of Ars==h11em 65 64 64 e

U-235 Enrichment (w/o ) '-

2.10 2.60 3.10 L

Final Averaae Burnup (MWD /MTU) 19.415,

19,824

'14.401 i

i L

5 43(072390)/6 ZD790 n.

[,

~'

~

~ ~,

g;p,14.E *; it-

- 4"

<w y '.

l 3

I

-34.* y.i[

D,-

U 4

'2.0 CORE CONFIGURATION l

L i

2.2 UNIT 2 CYrtE 2 CORE INFORMATION (Continued)'

y_

tThe UnitL2 Cycle 2 core configuration is illustrated in o

Figure 2.3.. Cycle 2 contains.4 regions.of fuel. Table:2.2:

t

)

4

.g shows the Cycle 2 Fuel' Regions.

In addition to 53. rod

,l centrol cluster assemblies (RCCA's)',' 768 wet annular =

1 s

bu/nable absorbers'(WABA'S), consisting.of'approximately'14' I

(f Iw/c B C,Lwere inserted to reduce peaking factors, maintain a.

4 negative moderator temperature coefficient, and to reduce

i the: residual boron-defect at the end of cycle life. Refer-to figure 2.4 for core insert map.

j Vantaae 5

'I Regions.4A and 4B consist of fresh Westinghouse. Vantage 5 fuel:

[

t assemblies. Vantage 5 incorporates six-design. changes from the 4

existingffuel.

s 1.

Removable ~ top nossle for ease of reconstitution.-

2.

Additional / plenum ' space to allow for extended burnup.

}

3.-

Natural uranium axial blankets at top and bottom of each

\\

fuel rod.

4.

Intermediate Flow Mixer (IFM) grids to improve DNB margin.

4 b.

43(072390)/7 ZD790 o

,~

2

.o 4

f*f, U

f

'ifd',!

D'.1

f.. ' s >

i s

_2'.0 CORE CONFIGURATION (continued) d 5.2

-Integral _ Fuel Burnable-Absorbers.(IFBA);to f

y Li "

t-

. eliminate residual; penalty f rom burnable! absorbers.<

)

. Debris-filtering bottominossle.1 6.-

.y 1

6480 IFBi rods are included in the Cycle 2' loading pattern. -

s 4

d The: locations of assemblies with-IFBA rods'are shown in L*

-j

-s

,4 v

Figure 2.1.

Figure 2.2 shows-the config'uration of IFBA rods within fuel assemblies.

s J

.Three of the Hafnium'RCCAs. wore. replaced with Silver-Indium-Cadmium RCCAs.. Replacement was necessary.

~because the three Hafnium RCCAs were not Eb'le to be inserted

~

into their respective fuel assemblies during component.

d shuffles.

The'new'RCCA identitles are R501, R502, and j

l

.R554.; They~are-located in core' locations'F14, CS,'and D4.

)

ll respectively.

i

~l X

j I

l, 4

7 h

43(071790)/8

[l ZD79G J

o

~

-. y;c c :mc~; a rs s~..-

~

- -[

,. ('

~

.e 2. -J. '

' d td' l

.x ;

t

  • *:.-i

.2:

y.

~

~ Table 2.2

~

BRAIDWOOD. UNIT 2 CYCLE'2[.

~

. CORE REGION DESCRIPTIONL REGIN 2 '

REGIOC 3 REGIN 4A REGIN 4B l

'N==har of As--N11es 45

_ 64 40' 44

~

(

U-235 Ecric h nt (w/o) 2.600 3.107' See Bote'l' See Mote'2'

~

i l

l

- Loadina (MTU) 19.035'-

27.072 17.001 18.702 Note 1 4A IFBA Rods

' 3.8006 4A Non IFBA'. Rods

' 3.'8114-1:

4A Arial Blanket

- 0.7472 l

l

- Note 2 4B IFBA Rods 3.5913 I

4B Non IFBA-Rods 3.5977

- 4B Azial' Blanket 0.7472 l

I 8

43(071790)/9' ZD79G.

+

=+v ee 9.

f-e e w.9 4.-'

3_._-_ _, _. _ _ _ _ _ _ _ _ _ _ _ _ _ _. -_ _, _ _ - _ _ _ _ _.

f p,___

g__.. _ _

4 n,,.gp,3..gg;pq g

.,,,g_

p,g

~

(n iy p!

{

3. s " 9,-

i 1

.;f. > f[

i I

p Fig. 2.1-'

y A

1 me=h e(Sources and Burashie Absorber Reds in Cycle 2 :

y-E

-R.

'P N.

M L

K J.

H 0

F E-D C

0 A

i 100

.;7 1

j 2

1001 1001 1601 80!

1601 1001 1001

-4

+

3 80!

160!

24A SS-24A 160! 80!

1601 24A 100I 24A 160!

]

100!

24A-24A 24A 24A 24A 24A-100!

i 1901 24A 1601 160!

24A 1001

~!.t

'601 24A 24A 160!

24A 160!

160!

24A.

1 90 i

270 501-1001 1001 80!

y 1601 24A 160!

24A 24A.

1601 24A 160!

t 1001 24A 1601 1603 24A 1001 1001 24A 24A' 24A-24A 24A 24A 100!

j 160!

24A-100!

24A 160!

+

13 801 1601 24A-24A 1601 801 1001 1001 1601 801 1601 1001 1001 t

15-0 i

ss SECONDARY SOURCE:

+ PREVIOUSLY IRRADIATED XI FRESH ASSEM0LY CONTAININO X IFOA R00LETS m(.

XA FRESH OA CLUSTER CONTAINING X-R00LETS D

l 5

9 a

i.

-a p.

.L' i

1 7::.;s 1

1 s

Fig. 2.2 i'

1 i'.'

. IFBA Rod Arrangement in a 17 x 17 Fuel Assembly.

1

"~

1(80 IFBA Pattern) a r

i e e e

e e

e e 1

o 'o X

X X

s 's L

X e..

e

  • X L

e e

e e e el e

e j

X X

X X

X u

u e

e e; e e e e e e e e

a o

e p

e e.

e e e

'l L

X X

X X

X e e e

e s e e.

e, e e e e e

I X X

X X

X 3

e e

e e,

el el el el B.

I X

e Le-

  • 1 st X

e-o X

X

.X e

  • e e e

e et e

e; e a

l 1

L 8

IFBA rod Nonpoisoned rod Guide tube l'

k l

location of Fresh IFBA Rods In Assembly l :-

I l'

\\

-c 10 ktwe e4 2
  • J s+--.

---m

m 8.

y i

p,

=...

]

lMij.

' *[

g 5

~r s

g.

. 3. ;

' Fig. 2.2 (ctd) 1 J

.h

!!'a

-j L

IFBA Rod Arrangmentin a 17x 17 Fuel Assembly 1

L

'(100 IFBA Pattern) c

'[

l-o e e.

e el e re e e j

e e X

X X

I e e i

X e te fX e

e e r e e e e ei e

X X.

X X

i X m

. e e,.

. e sie e

o o

e e e, e e e ele e

X X

X X

X i

L:

e e s e.

ele e

e e\\ e!

e. e e e ele e

o X

X X

X l X e,

er lelel elel lei e

L le LX l

ele l e-e X

et e e X

X X

l e, e 1

.! ale.

. e e e ele e e l

1 4

1 a

7 IFBA rod Nonpoisoned rod Q

. Guide tube h,

l-p 19 i

11 l

l Y

_ ~...._

. p, ;

s., -.

g

qq c, ;

q, y lv y

y

. rig. 2.2 (ctd>=-

i IFBA Rod Arrangementin a 17 x 17 Fuel Assembly

- (160 IFBA Pattern)-

k e e G

l ei e e e e-. :. e' e o.e

,I e S

  • e e el e' e :*

e :e e el e el el.

X X

X e e-o' l:

el e

-X e.

  • e X

el e o ce e

e e,

I i.

e X

X X

X X

e e e e e e e s

e e.

e e,

e e

e. e e e
e. e X

X X

X X

e t

c e, e e e e

e, e e s e e e e

s, e e s e

?

X X

X

- X X

e-e,St I lei e el is-el le, e, e e re X

elel

  • Ie-X ele i

X X

X s

ol e e e e e e e e e e.

... e e<

el e e, * * *. *.

e,

  • e e e.

i ex O

IFBA rod Nonpoisoned rod Guide tube s

12 i

( t-i

- - - ^ - - - - - - - - -

^-~

j, 4 ' f

^ -

I 3

i d

~ Fig. 2.3 6 9 %, f, L BRAIDWOOD. UNIT-2 CYCLE 2 RE010N NUMBERS AND ASSEMBLY-

.............................ID'.S RD P-N M

L K=

'J H

0 F

E D

C B

A k

l lii0 2-3 3

3 3

3 2

R59H $39H $37H S46H $35H $29H R41H 1

3 3-45 4A 4k 48 4A 4A 48 3-3 2

$21H $23H T43X TOSH TISH T56X TI8H T28W T59X $40H $61H 3

45' 4A -

3 4A 2

3 2

4A 3

4A 48 3

3 i

$10H 771X T29H S12H T02H R05H $30H R48W T37H $01H T08W T73X $19H

,1 3

4A' 2

48 2

2 48 2

2 48 2

4A-3 4'

$50H T23H R52H T42X R29H R12H T81X R39H R45H T48X R55H T24H $64H 2

48 3

48-4A-3 48-3 48 3

4A 48 3

48-2-

5 1

R37H T66X $45H T67X T20H $41H T63X $24H T64X S26H T21H 755X 553H T58X R14H 3-4A GA-2 3-2 4B 3

45 2

3 2

4A 4A-3 6

S$1H T14H T17H R51H S42H R27H T41X 548H T70X R38W $38H R42H T01H T27H $43H 3-4A 2

2 48 48-4A 2

4A 48 4B 2

2 4A 3

7 SOCJ TI3H R03H R50H T54X T50X T10H R46H T34H T78X T76X R28H R35H T32H $62H R

' ~ 10, 3-48-3 48 3t 3

2 2

2 3

3 GB 3

48-3-

8 270

$52H T69X $63H T84X $34H $11H R53H R22H R$6H $07H S14H T68X $33H T65X $54H 3-4A-2 2

481 4B 4A 2

4A 48 48 2

2 4A 3

9

$28W T26H R57H R62H T75X T49X T40H R60H T25H 780X T47X R20H R61H T22H $49H

.c

_i q

3 4A 4A 2

3 2

48 3

4B 2

3 2

4A-4A 3

10 547H T31H T09H R31H S32H R32H T57X $58H T74X R21H S31H R36H T36H T07H S36H

-l 2

43-3 4B 4A 3'

4B 3

4B 3

4A 48.

3 45 2

11 R34H 762X 556H T77X T16H S17H T79X S16H T83X

$18W T30H T44X S25H T82X R44H 3-4A 2-48 2

2 48 2

2-48 2

4A 3-12 515W T19H R19H T45X R25H R04H T52X R02H R08H T46X R54H T33H $20H q

3 48 4A 3

4A 2

3-2 4A 3

4A GB 3-13.

S55H T53X T35H S09H T39H R$8H S22H R40H T04H S02H T38H T61X $13H 3

3-48 4A-4A 48 4A 4A 48-3 3

14 S03H SO5H T60X T05H T11H T51X T06H T12H T/2X $59H S27H 2

3 3

3 3

3 2

15 R18N S08H $57H $60H S44H SO4H R23H 0

' REG RE0!0N NUMBER ASMID ASSEM8LY ID E

13 IL

-e.

- - -- w

~ - -

Lfp

,q, y.

e g i.l

'3

>h

~

i

\\

.v sk?/ -

k.

j g

i, i W

Fig. 2.4 BRAIDWOOD UNIT 2-i#

CORE INVDITORY MAPc L

Cycle 2.

j

\\-

t it 1P N;

M L

K J

N-G-

F E

D C

3 A

l 1

N32 N36 l

-Loop 3 '

180' R5qW 589W 577W 54+W SISW 529W #4IW l' ~

lie p 2STO 2ftD 1940 Sl+P 220 0 848D s

SLIW slow T49%

yd TISW T ISSP R91 1980 62 132 D y9x T864 T20d Tf't 540w isIW N44 ysg.

u,9 D R90 266D Ruoc IffD Slow T9tX T294 ygg 702N MfW fle d g4gw MN SetW Toed Trit SIN 3-

.t 192 0 24fD tb4D k 61 ' sMne>R% IUDD nec titlem 195 2190 26tD 1689 Sfow T23W #f2W T42X E298/ fl2W 781X RJ9W f46W T48X ffTW rf4W 564W 4

KIbb 34SD RSS 24P44MI *

  • 2sID sLE6 101D lir4D sePcMRss4 1989 Root V'

tarW Tnt S+SW T69x T2DW $44 W V6SK sn*N 76 6

$34rWTild Tfft

$rgW 7gy c.14 N 5'

sso{

ISip I

isvD /4/D 274 storskMe% 218P EYl%

lb9 D 8+9Fthm I440 # 2 *' " gS02 p

5Fl4 Tl4w Ti9W Rf/W.f42W r2sw T4tx

$40W T!*x Rgsw sssW R44.W retw ripWsegw 6

i t+sP RLA ronw isfD ff6 D Rbs 18DD R 8 2. 211>

n t,7 le1D 1710 2 val 4 @l

30 9 s

[,

sesw Tl1W tsw %M WW W

N0x M M

RWW %

SG2d 1

\\

14ID 2149 g$$

199 9 stNan 31%p St9YM 16fD t9Shed If?P RN*lhen' 19fo gpg 1090 te+ D, _up11g ff2W 769X $61W 784K 534 W SilW d5'JV #22W fr6W totw st+W Te#x fifW T6fx if#*e *'8 h,

90

sv6p R72

&t D R93

/6/P RBI

/49D R b3 /sa# nu lf10 R iol 14AP R48

/72b 270'-

l 6

$2sw TE6W ggpw 96?W T9Cx T49%

TNN bcW T2fW 700K T49K tsoW gggy Titet $49W 9

(!

14 ID ff6D R5V 1669 N#Fata 19eD 14fjup /t##

14r36Aq ' 26ep ag;fe,1993 gn 244D f4fp 641W Tild Tc4W R0lW: $13N SSIN tl6w rssw Tb9W fysw loi til >

Rics tWsw INP 609D $1-w Tf9A

$$gw 19+ x.

1999 RHZ Lipp hg 199D iff? 24 MORN St+>

U H4W filx $fg,w 799K TibW SitW 1Fff Sik W T045 ft9W T506 ft4K $3fW TOLE R44W 11' (i

Jef P -

20 $P R76 3# NifN b 169 9 Bd4' JAW 16#D BM/44h /67b "^r?N R 69 2ftb /970

{~

Sigg Tate gjgw T46*X tafW 404W Tf2x n2W ngW 746 1 pggy TE9w 12 jl

,ga y k ie ISIP Rib ^

R$!)Cen 14 %

lb4D R 69 10/O ffCD CHE% Al00 $11>

R%

l3 fifW Tf(X T16*W 509 W Tf1 W #fter 132W R48#At T5fW 583W T53,1 76fX il3W 13 p

140") 2540 267P #83-8475 WRH

  1. ff +D R84 s+M6M98 18ep 261D IffD-SolW tof a 76ex Tofw 7llW yfix 706 W TitW 791X fr9W Sf ?W

~

14

[.

N41 ff9 P R70 *

  • lD R%9 286D RS?- 246 7 (50/ 19tD Ri2 IF+P N43

'~,

gig W So# W 55?W 56cW 5 ++se Sof d (21W 15 1

l[_

to?b thiD 29GP ITGP I?op tf2D tpgp W

= LOOP 4 0'

LOOP 1 i

j

+

North

,7 0

l

~.

14 l

i"'

WQpl].

i s

w

'.. i bhi@$

EP '

4-a s

1 e y

o,-

U.:

3 Y4 5

~

l

.]

4 m

-3;0 CONTROL ROD DRIVE SYSTEM n ;

i s')

The~ control' rod drive = system wasitestedLand verified.to.be' A'

.g lLj je operating prior lto Unit 12 Cycle:2 startup.. Tests were performed u-(

to' verify / proper operation'of the bank overlap unit,;the slave
l

~

. cycler and the rod drop timing.

d

'j

-lb 1

3.1 CONTROL RQD DRIVE SYSTEM CHECKOUT 1

1 e

7

.The bank _ overlap checkout procedure demonstrated the ability of, j

1 S

the overlap
unit to St p the contzw2 rod banks in a

?

predetermined sequence for a uniform reactivity.

j insertion / withdrawal. The slave. cycler timing procedure H

-l

verified the proper sequencing of the rod drive' coilf c'urrents i

Eduring the withdrawal and insertion of' rods in each of the rod' l

Ldrive-power cabinets. 'From the. slave cycler; traces, the. coll-

-: voltages were also verified for each powericabinet. Tho'co11 I

voltages measured,were found'to be.between10.600 mV and 0.438'mV'

for the lifti stationary and' movable gripper coils as expected.

qThese voltages correspond to:the' vendor'specified currents of.35 to 48' Amps on'the lift coils and-7.0 to 9.6' Amps on the

' stationary _and movable gripper coils.

l l

l l

/>>

15 i

.p-43(071790)/10 ZD79G

r ;

. i :-

mm h; k l,;..

a aPLRNTINAMEt BRDWD2:

4"'/D

.f, J : TEST;0PERRTOR:i _ ;DCL WIG Tab 1') 3.1 -

  • l r 'S?k..l REACTOR OPERATOR:; KEVIf4.

V w DTEMPERATURE:. 559l DEG F MAX:. 551, DEG F MIN'

'M "1

  • C PRESSURE:

'1850--PSIG MAX-18003 PSIG

' MI N --

FLOW:RRTE:

=1001:% FLOW' MAX'

.100( % FLOW. MIN:

DRTE: 5-24,-90' 3

j

'TRBLE/0F; RESULTS:,

h jX9' DP.

DRSHPOT'EN RYt TURNAROUND ROD-DP. DRSHPO* ENTRY' TURNRROUND.

.l

  • 7f'

~

' : TI ME '.( MSE C ) '

TI ME (MSE C )

TIME. (f1SEC)

TIME (MSEC)

-l g.$

D02 :1; 1464 1904'-

F00 1

1 4(10 1880=

B12 - V 1,

'1452-1832.

KOB 1

14do-1860

'j v.

'M14; 1:

.1478

.1868

'PO4i 1 1434 1864

.l

' B04

.1'

.1446' 1876 F02

'1 14 4 1774

. D14 1L

-:1470

'1890 Bio 1

- 14;:2 1772' l

P12' 1 1430 1840.

K14 1

14(;4 1844-

'1 M02 1

1466 1866 P06 1

14:18 1788

.G03.

1 1448 1848 B06 1

14:10 1800 C09 ~ 1-

'1434 1824' F14 4

15:16

-1966-

^

J13 1

1442 1852 F14 3

15:8 1958

'N07 1-

1454 1864 F14 2

1588 1978 F14 1

15!i6' 1986 j

g P10 1

1410 l1770

'K02.

1 14:16.

1776 y

.C07 1 1

?1456 1816 H02 1

14 :4 1794 G13' 1 1516-1946

'B00 1

(14:16 1806-NOS 1'

1456 1856 H14 1

14:12.

1792 J03 1

1478-1930-POS 1

14:0-1790 E03: 4L 11532 1962 F06 1

14!i6 1956

-1966~

F10- 1 14(10 1F E03.'3<

-1536-LE03' 2:

1536 1966 K10.11
1,4 (I8 165d E03 - 11
-1534 1964 K06 :1 14:18 1838 C11' 1 1502' 1922

'L13 1'

145d 1844 i

N05c 1-1464 1884 I

l" lC05 4 1526

'2036 D04 4

'15d2 1962

'C05-3'

'1530 2040 D04

-3 15:14 1984 Y

COS

'2 1532 2042' DC4 2

15:16 1986

C05/ 11 1532 2052 D04 1

1514 2014

.{

E13

-11 1488 1900 M12 1

14!iB 1838 j

N11t, l' 1444 1874

,j

't LO3: 1 1484 1994

- i LH04; ' 1,

1504 1884 D12 1

1480 1830-1 4

1D06' 1--

1448 1828-M04 1

14(.0 1850 i

'H12 1:

1416 1786 H08 1

14(10 1860 M00 > 1.'

1450 1810 4

I 5

LH06'11:

1470 1900 H10E 21' 1450 1860 4

]

-MEAN: 1460 MSEC TWO SIGMA LIMITS: 1398 MSEC RND 1522 MSEC l

RODS; OUTSIDE LIMITS: F14 E03 C05 D04 L

16 m

O f..:

o

,,e y

byL.'p I

3.

f l3.2; ROD DROP TIME MEASUREMENTS

.The rod-drop > time. measurements demonstrate that'under hot, fulli

-flow conditions,~all rodJ will enter the dashpot region of.the fuel assembly within 2.7 seconds after.the start of decay of the'.-

stationary gripper coil voltage 1as'specified under Technical

_ Specification:3.1.3.4..The shorter

  • drop time. recorded was-for RCCA P-10, which was 1.410 seconds..The longest drop time was.

for RCCA D-04, which was'1.564 seconds.

Four RCCAs fell outside the two standard deviations criteria from the meanirod drop time-of 1.460 seconds and were redropped an additional three (3)

^ times for repeatability purposes. Table 3.1 is a summary of the rod drop-time measurements for Unit 2 Cycle 2 Startup.

4.0 INITIAL CRITICALITY ~

The-Jnitial-controi' rod. withdrawal. began on May 25, 1990 at 0138 hours0.0016 days <br />0.0383 hours <br />2.281746e-4 weeks <br />5.2509e-5 months <br />.

Control-rod withdrawal stopped with Control Bank D (CBD)

-at 180 steps with approximately 100 pcm remaining worth.

Dilution to ci acality began at-0327 hours on May 25,,1990 with I'CBD at 180 steps with an initial boron concentration of 1599~

ppm.

An Inverse Count Rate Ratio plot was maintained as a function of time and primary wate.-added. Unit 2 Cycle 2 l

initial criticality was-achieved at 1055 hours0.0122 days <br />0.293 hours <br />0.00174 weeks <br />4.014275e-4 months <br /> on May 25, 1990.

The critical rod position was 176 steps withdrawn on CBD and RCS

.; 1

-boron concentration of 1181 ppm.

17 43(072390)/11 ZD79G i}

(

~

,~

'100 f

y> > ', -

't 5.O'1110 PONER PHYEICE' TESTING

)

Eero power physics testing was completed on May 26, 1990. All t

1

. Technics) Specifications and st'oty acceptance criteria were met.

-s.

i The Zero power physics tests included I

1.

Boron Endpoint Measurements

2.. Isothermal Moderator Temperature Coefficient Measurements f

3.

Rod and Boron Worth Measurements - Rod Swap' Technique i

4.

. Shutdown Largin Verification 5..

Low Power Flus Map (30% RTP) l i

f

.c' f

P 18 4

43(071790)/12

.7 zo790 d

.4

h'*

' ib 5.0 ZERO PONER PHYEICS. TESTING 5.1 BORCM ENDPOINT MEASUREMENTS

g The purpose nf this test was to determine the critical boron concentration for the following rod configurations:

1.

All Rods Out and,

?

l 2.

Reference Bank (Control Bank C) Fully insert.ed The reference bank is normally the bank with the highest 1[

predicted' worth when inserted in an unrodded core.

Since CBC l

p had the highest predicted worth, it was used as the reference 1.

bank.

The boron endpoint results are listed in Table 5.1 below and l

were well within the design accepta9co criteria.

TABLE 5.1 L

BRAIDWOOD UNIT 2 CYCLE 2 Li-l BORON ENDPOINT DATA l-l Design Acceptance Condition Measurement (ppm)

Criteria (ppm)*

ARO 1198 1189 A 50

=-

CBC (IN) 1099 1088 1 50 l

1:

[

I

  • References 1 and 5.

l i

43(0723901/13

.ZD79G-L'

M"-

'Q

.5.0 ZERO PONER PHYSICE TESTING 5.2 ISOTHERMAL / MODERATOR TEMPERAWRE. COEFFICIENT MEASUREMENTS The purpose of this test was to measure the Isothermal Temperat*<e Coefficient of reacti'ity (aggo) for various cooldown and heatup cycler within the temperature rsnge of reactor startups. The results of these measurer.ents are shown below in Table 5.2.

All measured values were within I

the design acceptance criteria. 'The Moderator Temperature Coefficient (amod) was determined by accounting for the doppler heating.

The value of the doppler temperature coefficient.(-1.70 pcm/*F, Ref. 1) was subtracted from the

. measured ag,o to determine amod'

.I 1

It was found.that amod would remain negative throughout the cycle.

As a result, no restrictions were placed on plant operation. Refer ts the MTC values listed in Table 5.2.

TABLE 5.2 ISOTHERMAL AND MODERATOR TEMPERAWRE COEFFICIENTS MLSUREMENTS Control Bank D Average Is3 thermal Cycle Position' AP/6TAVE Moderator Co9fficient MTC (Steps withdrawn (pcm/'F)

(pnm/'ri (pcm/'F)

Manaured** Pradletade Cooldown il 209 14.0 / -5.5

-2.55

-0.351 Heatup 81 209

-14.0 /

5.0

-2.80

-1.362 A

-0.601 i

'Cooldown 62 209 14.2 / -5.0

-2.84 2.00

-0.664 Heatup 82

.!O 9

-15.0 /

5.5

-2.73

-0.694 AVE ITC

-2.73 AVE MTC

-0.578 j

1 l

0 Predictions from Referenct-1 and design acceptance criteria from Reference 5.

l 00 Corrected fer Partial Bank Insertion, Temperature and Boron Concentration.

20

~43(072390)/14 I

ZD79G e

,w7:wa

-+

-=

C' d

~

'5.0 EERO 1 GLEE PEDfEICE TESTING (Continued) jy1

[

7; ? -

I 4,',,1 a, L 5.3 ROD AMD BORCal. WORTH MEASURBERITE H

1 The purpose o'f this test was to determine the diffsrential'and 1

integral. worth of the' reference bank over its entire travel in an unrod6ed core and to determine the integral worths of the

, )?

remaining banks usJng the rod enchange method.

Adequate j

i shutdown margin was verified based on the rod worth measurements i

meeting the required acceptance criteria and performsace of a i

shutdown manyin calculation assuming rods were at the rod j

l Insertion limits.

i

(

1 s

Ihe rod exchange technique required calculations by NFS s

'(Reference 2) providing estimated critlaal positions of the reference bank af te-enchange.with the bank being measured, P

h,, and the assorlated correction f actors, u,.

The measurements were obtained-for three reference bank positions:

a)

Initially fully inserted position, (h )o

]

M Initial a

3 b)'

Critical position after exchange, h c)

Final fully lurerted position, (h ) Return

'I m

]

\\

21 43(072390)/15 ZD79G r--_-

m

.m m.m.

t.. y.y

. 7 y

b[- 'S ' >. '

j

'.. c

.3 t

f

[.i.;,

y : Q : 'j.

{::

j F.0 ZERO.. POWER PHYSICE. TESTING fcontinued) 1' l

- 5.3 ROD AND BORCat WOR 1H MEASUREMENTE (Continued)

I

.The worth of a measured bank, W, 1st l

l I

'Nf= _

- (Ap ), - et,(Ap ),

3 g

.L t

/,

where:

j

)

1)

/,= The total measured worth of the reference bank.

,h,?

R l

t

. Ap ), = The reference bank worth from 0 steps to the j

(

2) 3 D'

M Initial average of (h )o and (h )o turn l

M Re x

a

,t

)

M

~

, Ap )

= The reference bank worth.from h to 228 3)

(

2

steps, M

4) et, = A correction factor for the h worth due to the rodded geometry.

Rod worth measurements were perforn.d under the guidance of 1 -

Westinghouse Rod Exchange Topical Report in accordance with

~

Reference 4.

The' document states that the allowable percent alfference between measured and predicted reference bank worth is 10%; 15% for individual rod banks and 10% for the sum of all 4

measured rod banks.

For individual banks with a predicted worth less than~667 pcm the allowable difference is 100 pcm rather-than 15%.

22 43(072390)/16 ZD79G r

d

.~.

[ fA E 1

I ki d'fi

l a

,[ "

5.0 ZERO POWER PHYSICS TESTINr (continued 1' o:

5.3 ROD AND BORCBI WORTH MEASUAEMENTS (Continued)

Il J

The worth of the refJrence bank (CBC) was measured by dilution.

The percent difference between'the predicted worth and the 1

measured worth was -3.2%, which is well within the allowable l

limit as stated above. The.results of'the rod worth measurements are shown in Table 5.3.

Table 5.3 is the measured

.l rod worths based on the dilution measurement'of CBC.

1 Using the rod exchange technique, all control and shutdown banks j

were exchanged with CBC as required in Reference 4.

The largest

]

J e

. difference between a measured and predicted-rod worth was based

]

on the rod exchange results using the dilution data of CBC and j

?

was -10.4% for Control-Bank A.

However, the predicted worth of 1

Control Bank k'is less than 667 pcm and, therefore, the J

allowable difference is 100 pcm rather tht: 15%.

The measured difference was -46.4 pcm. The measured total worth of all 1%h banks, based on the'dllution measurement of CBC, was 5012.3 pcm which differs by -1.6% from the predicted worth.

All safety and r

design acceptance criteria were met.

i The rod exchange method determines boron worth data from the

~,

'dllution of the reference bank. The CBC differential boron worth was measured to be -9.14 pcm/ppe, while the predicted was

-9.30 pcm/ ppm (Ref. 1), a -1.75% difference. The design l

acceptance criteria associated with boron worth is A 15%.

I l

23 43(072390)/17 ZD790 l

1 3

-m m

- m-.

m 4

~

-g; r ;?

TABLE 5.3

a

~

1 ROD FYr'184NGE DEASUREBENTS l

DILUTION

~?'

l BRAIDWOOD UNIT 2, CYCLE 2 1

'~

Reference Reference Bank

-Benk Inferred Pre +1Lcted Percent Withdrawn Worth Worth Difference M

6 l'

BANK Inserted (b,),(steps) g y..

(Sy),

J4 )

xM)

"x-I h,

a 2

2 No.

ID Initial ~ Return Average (steps) x (pcm)

(pcm)

.(pcm)

(pcm)"

(pcm)

(%)

1 C

901.6 931

-3.2 2

D 22 22 22 146 1.08 14,3 355.7 384.2 503.1

.503 0.0?

3 B

22 22 22 196.5 1.28 14.3 160.2 205.1 682.2

~ 669 2.0 4

A 22 22 22 95,

0.91 14.3 535.9 497.7 399.6 446

-10.4-5 SD 22 22 22 130.5 1.09 14.3 404.1 440.5 446.8 428 4.4

~ !

6 SC 22 22 22 130 1.09 14.3 405.8 442.3 445.0' 428 4.0 H

7 SB 22 22 22 208 1.01 14.3 82.2 83.0 804.3 830

-3.1 8

SA 22 22 22 99 1.10 14.3 519.1 571.0 316.3-289 9.4 9

SE 22 23 22.5 130 0.92 14.9 405.8 373.3 513.4 569

-9.8 I

I i

M Measured Integral Reference Bank North, WR=

901.6 (pcm)

Total 5012.3-5093.0

-1.6 I

M I

R - IM ) ~ "x M I2s Calculations:

W, -W 1

I P

P

)

Percent Difference = (W,- W,)/W,x100 Note: Predicted values from Reference 3.

l 1

24 28(071790)/18 ZD79G l

.m.

,wn

,.w-

.. ~... -,-,_.._, _

_,m,__m m__m_.__-_,.__

m

...___m,,__m___.________...._.____,m._m.mm._mmm.m_____________.____.___.________m._._

l

,-[tl,1

)

1,d 'fil. -

\\

't

.- ? ?

q

. 's.

?,

.?i 0.0 AT PQsfER PHYSICS TESTING X

on May'28, 1990 at 0819 hours0.00948 days <br />0.228 hours <br />0.00135 weeks <br />3.116295e-4 months <br />, Unit 2 was synchronised to the grid for the first time during Cycle 2.

Power was then increased to 30% RTP and stabilised for the first Full Core Flux Map _(FCFM). Analysis of the results showed that the peaking i

factor Fay (corrected) exceeded Fay RTP in both the upper and 1

./

1 lower core regions. Technical Specification 4.2.2.2 required remeasurement of Fay within'24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after enceeding by 20% of j

~

,1 Rated Thermal Power or greater, the thermal power at which Fay was last determined. Other flux symmetry analyses performed on

']

I the flux map results were:

flus tilts based on the Symmetry J

l N

Check Edit and the Assembly F edits regionwise percent

]

'I differences between measured and predicted reaction rate 1

integrals based on the Final Comparison of Saturation Activity j

and PDQ Activation edit; and a symmetry check based on the Symmetric Thimble edit. Each of these checks were performed on the results of the flunmap. A flux tilt of 1.,0213 was measuredbasedontheassemblyF{Hedit.

All other parameters-l were within the acceptance criteria. Table 8.2, item 5, lists

>L the acceptance criteria associated with each of the parameters i

checked.

P 4

I 25 J

43(071790)/19 i

ZD79G t

RS

i;'

i F -4 y i

iin.

l l

.,.b? *

" E.

e 6.0 AT POWER PHYEICE TESTING (Contin;w.'

Reactor power was then increased to approximately.49% RTP and

'l i

stabilised for another flux map.

Power level was maintained i

E less than 50% due to the indicated flum tilt. Flux mapping was 1

performed at this power level to measure peaking factors and to

')

perform an incore-Escore Power Range calibration. Try was 3

measured was found_tp be below Fay (RTP). An RCS flow

)

3 measurement was performeo us required prior to operating above j

1 0

'75% power and F was measured and compared to its acceptance H

1 criteria. The checks specified in Table 8.2, item 6 were successfully performed on the flux map results.

)

)

Power was then increased to the 75% plateau and stabilised for j

unother flum map. The results of this flux map were acceptable.

Ascension to approximately 97% RTP was initiated.

At 97% RTP three flux maps were performed to measure peaking i

l factors and to provide data for an Ir.' ore-Escore calibration.

Fry was less than Fay (RTP). TheF{H8urV*illanC* wa8 *CC*Ptably.

performed also. The normal checks on the flux map results met the test acceptance criteria.

Additional peaking factor i

analysis / measurement will be performed at normal 31 EFPD Intervals in accordance with the normal surveillance requirements of the Technical Specifications.

i e

t 26 43(071790)/20 ZD79G L M u

-)

4 y

  • s.

.j is q

?,

6.0 AT PONER PHYSICE. TESTING'(Continued)

,' e

. a

i j

,l.

NOTE: DEFINITIONS OF PEAKING rACTORS TJ;;

J l

ray (Z):

Radia' Dambi~y Factor, is defined as the ratio of I'

. peak power density to.avea g: ;*ar density in the 3

horisontal plane at core elevation Z.

h Fay (Z)- (corrected): ray from INCORE

  • 1.03
  • 1. 0' l

1 Fay (Z)

(Limit):

l'.860 (1 + 0.2 (1 -- P)] for redded planes j

(Lower Core Region)

.1 l'.823 [1 + 0.2-(1 - P)] for rodded planes (Upper Core Region) 1.704 [1 + 0.2 (l'- P)] for all unrodded planes i

i Ng Nuclear Enthalpy Rise Hot Channel Factor, is F

detlaed as the ratio of the integral of linear

~

power along the rod with the highest integrated j

5 power to the average rod power.

.l FN=TN from'INCORE

  • 1.04 g

rL(Limit)- 1.55 (1 + 0.3 (1 - Pn for Ora ruel i

1.65 (1 + 0.3 (1 - P)] for Vantage 5 fuel I

- r (Z):

Heat Flux Hot Channel Factori is defined as the g

maximum local heat flux x a the surf ace of a fuel rod at core elevation Z divided by the average fuel s

rod heat flux allowing for manuf acturing tolerances on fuel pellets and rods.

r (Z) = r (Z) from INCORE

  • 1.03
  • 1.05 g

g r (Z)-(Limit) = (2.50) (K(Z)) for P > 0.5 g

P 4

5.00 (K(Z)) for P 1 0.5 3

Where P is the traction of Rated Thermal Power i

j l

27 43(072390)/21 w

20793

, ' i. y

.e.

., ~ ;'

TABLE 6.1.

FXI MEASUREMENTS DURING POWER ASCENSION I

BUENUP UPPER (W F TN (Mr f TasTT FZY trunerTum I

f.IBEIT Frnr map 3 primar*

M/BffU FXY res&K.

.m BN20201 30.O 83.4 1.7592 1.9426~

1.7144 1.9426 BW20202 49.1 138.0 1.6781 1.8775 1.6421 1.8775 BW20205 75.2 240.2 1.6837 1.7885 1.6390-1.7885 BW20206 96.8 381.7 1.7091 1.7149 1.6303 1.7149 Note: All values are for unrodded core planes.

28 43(071790)/22 ZD79G

,%.s_,

.9-

.., +.,

,,,,,,g..,_

__,_,]

- ~

.L c. T,

-_e.

TABLE 6.2 FLUK MAP CHARACTERISTICS Map Power Level.

CBD Position

'Incore Asial Burnup M=hr Date (Stena Wi+hdrawn)

Offset

(= =/MftI)

BN20201 6/1/90 30.0 197 3.187 83.4

_3f20202 6/12/90 49.1 216 S.784 138.0

  1. 20205 6/17/90 75.2 208

-1.108 240.2

.BN20206 6/20/90 96.8 220

-2.668 381.7 Note: Flux Maps BN20203 and BN20204'are not included because they are taken under unstable conditions as a part of an Incore-Escore calibration.

29 43(071790)/23 ZD79G

? I'

=

-=

. -.2

.g 3_,.

- _ _ f :.

9

~

~

  • TABLE 6.3

~'

Flux Map Results Measured Peaking Factors

  • Peaking Factor Limits

~Incore Quadrant Tilts

.. y 3 N

T N

Channel Channel Channel Mann=1 Map Fg F

(Z)

Fg Fg (Z) 41 42 43' 44-g Number OFA 1.4627 2.0555 1.8755 4.687 1.0034 0.9900 0.9853 1.0213 BN20201 V5.

1.5908 1.9965 0FA 1.4559 2.0791 1.7867 4.675 0'9969 1.0055 0.980F 1.0173 BN20202 v5 1.5497 1.9020 0FA 1.4558 1.8176 1.6553 3.112 0.9977 1.0029 0.987'.

1.0122 BW20205 V5

'L.5576 1.7728

(

OFA 1.4476 1.7837 1.5649 2.414 0.9967 1.0014 0.9913 1.0106

~

l BW20206 V5 1.5585 1.6658 l

l

  • Includes uncertainties.

Table value may not be core peak b'ut is value closest to limit within the operating envelope.

e l

30' l

43(071790)/24 l

ZD79G

~

x

. Fig.J0.1

~

BraidcoCd Unit 2 Cycle 2

~

Power History

=

100 95 r-90-II II 85 I

I 80 I

l I 75 i

r 70 65 l

60 i

55 3

50 J

2 45 C

I I

40 I

35 30 25 J

20 15

,A b

10 I 5 I O

27 2

9 16 23 27 May June 31

- - - - ~.

s

-h h i 4 ' L ' " ' ' ',i l

I

i 7.0 REACTIVITY AMCMkLY/BORCN FOLLOW j

A reactivity anomaly check was performed following the startup 1

I of Unit 2 to fulfill the Technical Specification. requirement of 1

Section 4.1.1.1.2.

This check showed that at a burnur ' f 685

\\

MWD /NTU, or 16.4 EFPD, the measured and predicted cond.clons differed by only 0.27% AK/K at a core average burnup. This is well within the 1.0% of AK/K Technical Specification limit.

n l

J

-1 1

Figure 7.1 shows the plot of r.easured and predicted critical

.j i

boron concentration versus burnup.

The measured values are l

1 1

corrected to all rods out, hot full nower conditions using tho' i

l.

Westinghouse FOLLOW code. The design acceptance criteria of 1 50 ppm was met. -The measured values are also within the l

Technical Specification requirement of A 1000 pcm about the predicted value.

1 e

0 4

32 4

41(071790)/25 Zt79G u

6 w -, -..

-s-m

-u- -. -

u c-,

-?*.

g.

~

9.y.,

I I

Fig. 7.1 j

1 BRAIDWOOD UNIT 2 CYCLE 2 BORON FOLLOW DATA 1100 l

lI I

.l 1000 0-O h

R-

- {3 N

e 1

.O

.,900 J

1 N'

t;

.C

.J (p

4 P-U

)

1 4

s00 s

+

4

  • %+4+,++

+

t 700 T

l 0

S00 1000 1500 2000 2600-3000 3500 4000 l:.

BURNUP (MWD /MTU) l

\\

i l

BORON CONC. WEASUREMENTS CORRECTCO TO NOWINAL l

AND PREDICTED POINTS VS.

CYCLE BURNUP h

FOLLOW PTS +, SOLID LINE REPRESENTS PREDICTED PolNTS 1

i!1 ls

+

\\.

l 1

i s

t b

5 l;--

l,i 33

[

,i

'o

.A:,

e i.,

',, ~ e 1'

t, b

8.0 EUkbiARY AMD CCERCLUS1(Bl$

The Startup_ Testing Program was completed on July 2,1990 with satisfactory results. Table 8.1 has been included to provide a brief summary of the results obtained during the startup physics testing on Braidwood Unit 2 Cycle 2.

Table 8.2 has also been provided as a summary of design acceptance criteria and safety' acceptance criteria from Reference 5.

All design hcceptance criteria, safety accept.ance criteria, and Technical Specifications have been met.

Therefore, the Startup Testing Program is considered to have verl. fled NFS's analyses for Unit.

2, Cycle 2.

34 43(072390)/26 ZD79G

'4

. e;

't3~*.

j 14V"*i jut

' 8.0 StnethiY AND CCEICLUSICRI (Continued)

TABLE 8.1 I

PHYSICS TESTING

SUMMARY

)

em PAWiMrTER MritDREn

__ pratunen pmEn1CTED DIFFratMCE'*

l INTEGRAL ROD WORTH MEASUREMENTE focal CBA 399.6 446

-10.4%

l wh< <

2 7

CBB 682.2 669

+ 2.0%

1 e

CBC 901.6 931

- 3.2%

CBD 503.1 503 4 0.0%

1

.._KBA 316.3 289

+ 9.4%

I EBB 804.3 830

- 3.1%

j

.I EBC.

445.0 428

- 4.0%

1 EBD 44641___

428

+ 4.4%

1 EBE 513.4 569

- 9d%

TOTAL 5012.3 5093

- 1.6%

j ISOTHERMAL l

TEMPERATURE j

COEFFICIENT (pcm/*F)

-2.73

-3.06

'0.33 MODERATOR j

TEMPERATURE

__ COEFFICIENT focm/'F)

-0.578

-1.362 0.784 DIFFERENTIAL BORON

'j

-WORTH.ARO (pcm/ppe)

J

-0.14

-0.30 1.8%

ALL RODS OUT-HOT I

ZERO POWER CRITICAL

. BORON CONCENTRATION (pon)

__,__1198 1189 9 ppm CBC IN-HOT ZERO I

POMER CRITICAL BORON CONCENTRATION (ppm) 1099 1088 11 ppm ALL RODS OUT-HOT FULL POWER BORON CONCENTRATION (ppm) 738 768

-30 ppm F

See Table 8.2 for the acceptance criteria

    • Average values are given when parameter was measured more than once.

l 35 43(072390)/27 ZD79G i

s. ~ 8,0 tammRY AMD'ccmcLusItms (continued) j

~:n

/h V.

l TABLE 8.2 TEST CRITERIA M

eq

  • ti
,J Test-Parameter Test Criteria.

1.

WEP Critical Boron (Control Rods Withdrawn).

.t 50 ppm h2P Critical Boron (Reference Bank Inserted)

A 50 ppm 2.-

Differential Boron Worth (Boron Reactivity Coefficient) i 15%*

)

3.

Control Rod Worth Tadividual Bank i 15% or 1 100 pcm Rtview or Design Criteria whichever is

)

greater (for rod-swap, the reference bank should be l

within i 10%)

Sum of Banks i 10%

l Review or' Design Criteria j

l 4.

ITC 1 2.0 pcm/'T I

MTP

< 0 pcm/*r for entire cycle 5.

Flux Symmetry - Incore Flux Measurement (1 30% RTP).

a.

Using the Edit for Symmetric thimbles.

1 1 0.1 (10%)

Ratio of highest to lowest normalised reaction rate integral for each set of symmetric thimbles..

)

1 b.

Using the Final Compsrison of Saturation i 10%

Activity and PDQ Activation.. Regionwise (For unrodded j

percent differences between meas., calc.

core planes reaction rate Integrals for thimbles with only) i

> 0.9 RPD **.

c. -Using the Symmetry Check and Assembly TDHN

< 1.02 quadrant power tilts.

I 6.

Power Distribution.

i a.

Using the Measured and Predicted F edit.

1 0.1 RPD l

Ng 1

The differences between the measured and predicted FDHN for each measured assembly.

o b.-

Using INCORE edit " Difference in React.

< 0.05--

l Rate Integrals" value labeled "Std. Deviation".

7.-

Critical. Boron (100% Power) 1 E0 ppm NOTE:

Table is based on American National Standard ANSI /ANS 19.6.1 - 1985

' NOTE:

For ca3culating percent differences use (EI.e4 - 1) x 100%,

{

l Meas except when calculating percent differences for rod worths use (Mens -1) x 100%

Pred N

    • RPD Relative Power Density = Normallsed Reaction Rate Integrals or Tg L

36 l

43(072390)/28 LZD790-

.q' q

AY,.

' A ' 'i.. 'I. $

9.0 REEEr.AMCES I

1.

NFSR-0080,. " Nuclear Design Report for Braidwood Unit 2,

-l Cycle 2", May, 1990.

i 2.

CECO Letter, V.S. Noonan to D.L. Farrar, " BYRON /BRAIDWOOD I

ROD SWAP TECHNIQUE," September 9, 1986.-

3.

CECO Letter BR2C2/040, R. Chin to D.E. O'Brien, May 11, 1990..

)

I-I 4.

WCAP-9863 A, " Rod Bank Heasurements Utilising Bank Exchange", dated May, 1982.

i 5.

ANSI /ANS-19.6.1-1985, "American National Standard Reload-l Startup Physics Test for Pressurised Water Reactors",

)

approved December 13, 1985.

l 6.

Vantage 5 Reload Transition Safety Report for the l

Byron /Braidwood. Stations units 1 and 2, Westinghouse-

-J Electric Corporation, July, 1989.

j 2,

7 Final Reload Safety Evaluation Transmittal, Braidwood Unit 2 j

i

_ Cycle 2, January 8, 1990.

I

{

i

?

i t

I f

Y 1

.f w

b (Final) 37 4.

143(072390)/29 ZD19G.

.

Retrieved from "https://kanterella.com/w/index.php?title=ML20064A639&oldid=4445647"