NSN no $.one YANKEE ATOMIC ELECTRIC COMPA Y 2 4 /w wg 9

22
r , , 5)pplcmint No. 7 _( ) y :.idrndum No. 1 ' Telephone 617 366-9011 . no $.one /< NSN <- YANKEE ATOMIC ELECTRIC COMPA Y 2 4 WrR ,6 21 /w wg 9 . . arp . 20 Turnpike Road Westporough, Mosso!hu>sep- T I.29 12T' a , 01581 ,YAuxes 1, r;77;; - t ;<C$(c- - F{?* , ,Cy. Reguictory t * '" March e ,, k{C /' fg (C.n United States Nuclear Regulatory Commission > Washington, D. C. 20555 94R /gg (9 " Attention: Office of Nuclear Reactor Regulation g Subject: Core XII Technical Specification D.2.c. Eh * s/O 'l ' Reference: (1) License No. DPR-3 (Docket No. 50-29) / f (2) Proposed Change No. 125, Supplement 7, FG dated February 19, 1976. Dear Sir: With reference to a conversation on February 26, 1976 between your Mr. Burger and our Mr. Cacciapouti, enclosed is additional information in support of Reference (2). We trust that this information is satisfactory; however, should you desire additional information feel free to contact us. Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY j HW W. W. Johnson Vice President COMMONWEALTH OF MASSACHUSETTS) )ss. COUNTY OF WORCESTER ) Then personally appeared before me, W. P. Johnson, who being duly sworn, did state that he is a Vice President of Yankee Atomic Electric Company, that he is duly authorized to execute and file the foregoing request in the name and on the behalf of Yankee Atomic Electric Company, and that the statements therein are true to the best of his knowledge and belief. M44 / Armand R. Soucy Notary Public My Commission Expires September 9, 1977 80 111406 ) g o c ~ g.~,. 4 u ,

Transcript of NSN no $.one YANKEE ATOMIC ELECTRIC COMPA Y 2 4 /w wg 9

Page 1: NSN no $.one YANKEE ATOMIC ELECTRIC COMPA Y 2 4 /w wg 9

r ,,

5)pplcmint No. 7_( )y :.idrndum No. 1'

Telephone 617 366-9011.

no $.one/< NSN

<-

YANKEE ATOMIC ELECTRIC COMPA Y 2 4 WrR ,6 21

/w wg 9..

arp . 20 Turnpike Road Westporough, Mosso!hu>sep-T I.29 12T'a,01581

,YAuxes 1, r;77;;-

t

;<C$(c- -F{?* , ,Cy.Reguictoryt* '"March

e ,,

k{C /' fg (C.nUnited States Nuclear Regulatory Commission >Washington, D. C. 20555

94R /gg (9"

Attention: Office of Nuclear Reactor Regulation g

Subject: Core XII Technical Specification D.2.c. Eh * s/O'l

'Reference: (1) License No. DPR-3 (Docket No. 50-29) /f(2) Proposed Change No. 125, Supplement 7, FG

dated February 19, 1976.

Dear Sir:

With reference to a conversation on February 26, 1976 betweenyour Mr. Burger and our Mr. Cacciapouti, enclosed is additionalinformation in support of Reference (2).

We trust that this information is satisfactory; however, shouldyou desire additional information feel free to contact us.

Very truly yours,

YANKEE ATOMIC ELECTRIC COMPANY

j HWW. W. JohnsonVice President

COMMONWEALTH OF MASSACHUSETTS))ss.

COUNTY OF WORCESTER )

Then personally appeared before me, W. P. Johnson, who being duly sworn,did state that he is a Vice President of Yankee Atomic Electric Company, thathe is duly authorized to execute and file the foregoing request in the nameand on the behalf of Yankee Atomic Electric Company, and that the statementstherein are true to the best of his knowledge and belief.

M44 /Armand R. Soucy Notary PublicMy Commission Expires September 9, 1977

80111406 ) g o c~ g.~,. 4u

,

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l.0 INTRODUCTION '

The xenon multiplier was chosen to conservatively account for the

maximum transient xenon peaking expected due-to. control rod motion at

full powsr.

In the development of this multiplier, only control rod motion

above.75" was considered, since rod insertion curve limits the control

rods to this band during operation at the maximum allowable power level.

Control rod insertion below 75 inches requires a concomitant

reduction in power level -below the maximum allowable value. The reduced

load multiplier was therefore chosen to offset the increase in peaking

'

which could be induced by an increase in power level combined with

control rod withdrawal from below 75 inches to above 75 inches. The

'24 hour hold at the reduced power specified by this multiplier allows

sufficient time for the initial xenon caldistributio'n|''o accommodatet

itself to the new power distribution.~

,

. .:

The following approach was used in evaluating limits for this

Technical Specification:

A. Results for the Technical Specification were evaluated in

' terms of the ratio:

F (equilibrium xenon)

max F (transient conditions)

B. The F 's used were those for the assemblies containing the

hottest GULF fuel rod (assembly location C-4) and the hottest

EXXON fuel rod'(assembly location F-2).

C.- The maximum allowable core power level was assu=ed to be

600 MWt, evenLthough the application of item C of the Technical*

Specification may limit core power to lower values.

-1--

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2.0 XENON TEST AND' COMPARISON WITH CALCULA1 TONS.

On December 30 and 31, 1975' a xenon transient tes't was performed,

at Yankee Rowe to verify the adequacy of the three-dimensional nodal

cod 6 SIMULATE to follow' xenon transients.

The test was performed as follows:

A. The plant was at equilibrium conditions at 125 MWe, 250 MWD /MTU,* 1684 ppm boron and the Group A ceatrol rods at 83 inches. Poweri

was then r' educed to 33 MWe by inserting control rod Group A'

to 45 inches. This maneuver took 1.5 hours.*

i .

B. The load was held at 33 MWe for 5 hours.

C. After 5 hours, load was increased to 115 MWe by withdrawing

rods. This maneuver took 1 hour to co=plete.

]D. Full core traces were taken at the equilibrium condition, at

;'

reduced load and every six hours after return to power. In

,

accition, incivicual traces in ene asse=nites in locations

F-2 and C-4 were taken every hour for 30 hours after return,

to power.

The SIMULATE cockup of the test was as follows:

A. Core XII was depleted to 250 MWD /MTU, Equilibrium Xe was

built in at 125 MWe (407 MWt), with Group A at 83 inches and

1680 ppm boron.

B. Load was reduced in three steps; 363 MWt for 1/2 hour with

I~

76 inches, 249 MWt for 1/2 hour with rods at 62 inchesrods at

and 131 MWt for 1/2 hour with rods at 49 inches.

C. For the next 5 hours, load was kept et 105 MWt (33 MWe) and

the ro'ds were kept at 45 inches.

D. - Load was increased in two steps; 19011't for 1/2 hour with

rods at 56 incies and 336 MWt for 1/2 hour with rods at|

72 inches. !|

-2- l

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" E. For the next 30 hours, load was hel'd at 374 MWt (115 MWe)

and control rod Group A was held constant at 86.5 inches.

The comparison between calculation and measurement of the*.

relative axial power distribution at equilibrium conditions before the test

for the assemblies in locations F-2 and C-4 is given in Figures 1 and 2.

These assembly locations contain the hottest fuel rods in the Exxon and

Gulf fuel assemblies, respectively. The comparison of the relative axial

power distribution at reduced load with control rod Group A at 45 inches

is given in Figures 3 and 4 for the assemblies in locations F-2 and

C-4. A comparison two hours after return t'o power in the same assembly

locations is given in Figures 5 and 6. From these six figures, it can

be seen that SIMULATE gave excellent agreement with the test results.

For 30 hours after return to 374 MWt, incore traces were taken in

' assembly locations F-2 and C-4. Comparison of the calculated and measured

values of F are presented in Figures 7 and 8 for these assemblies.,

Again, this data showed excellent agreement between'the SIMULATE .

calculation and the measured data.

Based on the data taken and the comparisons made', it was

concluded that SIMULATE could be used to adequately predict xeno'n

transients.

3.0 DETERMINATION OF XENON REDISTRIEUTION MULTIPLIER

To determine the xenon redistribution multiplier in Figure 8-4

of the Technical Specification, a number of rod motion studies were

made between the rod insertion limits of 75 and 90 inches. The

studies were made using the SIMULATE model of Core XII at EOL (O MWD /MTU),

MOL (6000 MWD /MTU) and EOL (13000 MWD /MTU).-

-3-

.

l

|

1

|)

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= - . .~ - .- . - . . . = . -- . .-. .. . . -.- .__ - - . -

. t'

Y -

'.

i.

Using the critical boron at each' time in life the following transient

1 was calculated: |'

t. <

] A._ Rods at 83", equilibrium xenon, 600 MWT. .

i B. Instantaneously insert rods to 75 inches with power remaining

constant. .,

,

0

) C. Hold at 75. inches for 8 hours. .From sensitivity studies with, ,

'

! SIMULATE, it was determined that a hold between 6 and 8 hours|

j would give maximum axial ' peaking. !

i r

! D. Instantaneously withdraw rods to 90 inches with core power :*

,

remaining constant and follow transient for 15 hours in

one hour. steps. i

j For EOL, the ratios-of the maximum F, to the eqitilibrium values are

. given in Table I for the assemtlies in locations F-2 and C-4. With!

similar data at BOL and MOL, the maximum ratios as a function of

] lifetime were plotted. For added conservatism, a straight line was|

| drawn above the data to.be used for the xenon redistribution multiplier'

' in the Technical Specification. Figure 9 shows the calculated data and

the xenon redistribution multiplier presented in Figure 8-4 of the.

Technical Specification.

4.0 DETERMINATION OF REDUCED LOAD MULTIPLIER.

The reduced load cultiplier, Figure 8-5, was determined by typical

transients using the SIMULATE model of Core XII at BOL (O MWD /MTU),I

| MOL (6000 MWD /MTU)'and EOL (13000 MWD /MTU). All tra,nsients used the,

. critical boron at that' time in life. SIMULATE calculations were runL

as follows:,

s .

d

-4-.

!.

i

s

-e--,w s- 9 p w sn- we <,.---+,,ne-, , -e re ~ ~- - -r w 1-- , , ----e-

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(' !

-

.

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A. The initial power was 600 MWT with equilibrium xenon and.

control rod Group A at 83 inches.

B. Power was instantaneously reduced to 450 MWt and control

rod Group A instantaneously inserted to 45 inches. These

conditions were held for 8 hours.

C. After 8 hours, rods were instantaneously withdrawn to 83 inches,

and power was instantaneously increased to 600 MWt. The xenon

transient was followed for up to 100 hours in one hour steps.

'

To show the effect of this maneuver, the relative power at three-

axial positions in the core is plotted in Figure 10, node 3 which is

1/4 of the way up the core, node 6 which is half way up and node 9 which is

3/4 of the way up. Figure 10 presents the ratio of the average axial

power in'the node to the equilibrium value of power in the node, showing1

| how rapidly the oscillation is damped.

For assembly locations F-2 and C-4, the ratio of the maximum Fz

.

over the 100 hours to the equilibriue values at EOL is given in -

Figures 11 and 12 as a function of time. As can be seen, the ratio

starts at a high value and decreases rapidly with time. The inverses of

the maximum ratios at BOL, MOL and EOL were plotted as a T in Figure 13.

For added conservatism, a straight line drawn below this data is given as,

the reduced load multiplier in Figure 8-5 in the Technical Specification. ;

Application of this restriction insures that the maximum linear heat rate

during the xenon transient does not exceed the value in Figure 8-1 ef

the Technical Specifications.'

The requirement in the Technical ~ Specification for a 24 hour hold

came after a series of calculations to determine the optimum time at the

.

-5-

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- , - . .___ . . . - . _. . .

e

(,

.. I..

*

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.The 24 hour hold allows sufficient time for the initialreduced' load.; -)

xenon maldistribution; to accot:modate itself to the new power distribution. |*'

!i

The restriction ~in control rod location during these 24 hours assures

* hat the return to the allowable fraction of full power will not cause.,

additional redistribution due to rod motion in excess of : hat given in

Figure 8-4.4

4

- I

) ,

,

-.

i

.

1

4

4,

4

4

;<

.

4

)

e! ,

1

.

.-

1

5

1

,

-

. t

4

'

.

i

,

-6--4

.

, , , - . , - - __ , . - _ ., - , - , _ ,,,, . ,- ,

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- _ . . . - _. -. . .

EOL . 4' '' 'aatio of F ca.s Function of GrC.) A ,

Position and fins in Assemblies F-2 and C-4' For 8 Hours During Rod In'sertion-

Group A Position Time Ratio of F to Eq Value of F:(inches withdrawn) (Hrs) F-2 C-4

75 0 1.017 1.018 '

75 1 1.020 1.021

75 2. 1.027 1.027

3 75 3 1.032 1.033

75 4 1.034 1.035

i 75 5 1.037 1.038

75~

6 1.038 1.039!

,

75 7 1.040 1.041

75 8 '1.042 1.042,

: For 15 Hours After Rod WithdrawalGroup A Position Time Ratio of F to Eq Value of F(inches withdrawn) (Hrs) F-2 C-4

vu u 1.019 1.024

*

90 1 1.006 1.009, ,

90 2 0.991 0.997,

90 3 1.004 1.010;

90 4 1.017 1.024

90 5 1.024 1.0329

-

90 6 1.032 1.041

90 7 1.034 1.044'

90 8 1.036 1.047,

90 9 1.038 1.049,

90 10 1.039 1.049

90 11 1.040 '1.049,

90 12 1.040 1.049

; '90 13 1.039 1.048

90 14 1.037. :1.045'

90 15 1.032 1.038

4

- -- , , , --4 . e,.-- . n.- , ,, . , ,: , - , . .

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_. - - - _ _ _ .. . .- _ . _ _ __ . _ _ - - _ _ - _ . _ . ,,7,.,y,.

,,. -

.

.

-

.

i COMPARISON OF SIMULATE AND MEASUREMENT IN ASSEMBLY F-2EQUILIBRIUM 01.3TRIBUTION

~

l.40 guiiiiJs: e i e i e i i e i p i i i uus ; i e i i i u.u p.u u.u n.p.u.uu i e iiieieieiiu.o uiea;eiie>i.tu_ 1 40= =

5 5

1.30 L pr-- 2% .jI.30 ..

'E N 5.E 5

^.

1. 2 0 E. . 11 20E . i

5 .- 5

1 105.'

_il.10.

5- i.

: = <l.005., _it.00

5 .- 3'

2 5-

a-- .-

-

w 90 5.-s 5 .

.- . 5 90-.

5o E . 5 m-

. 80 E._i :.

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: c<c E 5- 1-~ =

- = n*

x . . / O :_.ct =

. i.70 g:.

:: :'

w E i

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-- :. . i.60

:

n 5- 5-.

(t -

a . 5 0 E.w :

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M 5 5

*40 3 35- SIMULATE Group A at 83 | aches. - 5*40 -

,

5 A Test Data Group A at 83 Inches 5,

.30 5. . .5.30-

- -05 5

*

-.

-

. 2 0 E. ..i.20*

: :: :

5 5.10 : : .10

5 55 5

. 0 0 (n , , , , , , , ; , , , , , ,_,., rb n rrri r -t i- rri i r r r r h43 ri v r T rh ri rrrr i r i . . . . . . . . I r r i , , . . . . : . . . . . . . . . i.00.0 10.0 20.0 30.0 40.0 5 0 . 0,- 60.0 70.0 80.0 90.0

*

CORE liEIGifT ( IN INCifES) -

3/3/76- _ _ _ _ _ _ _ _ _. ___ _ - _ _ , ._ _ _ _ __

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_ . . . . . _._ _ __ ___ __.-_._____m. . _ _ _ .. . . _ _ . _ _ _ __ . _ . - _ _ . _ ___ . _ -. .

.

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COMPARISON OF SIMULATE AND MEflSUREMENT IN ASSEMBLY C-4 .

EQUIt_IBRIUM OISTRIEUTION' I . 4 0 .u tu.u . . . . . . . . . . . ; . . . . u u p . . . . . u p i i i n n i . u.cp.c .u . . . . : . . . . . . . . : . . u . . = . ; = = = u.u.i__1 4 0

:- :.

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1 30 il- _il.30.

.= . == :-5. - 5

1 20 = nl.20= ='5 i-

1 10 E..

it'10_

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:

5 E i'1. 0 0 E.

.

il.00,_i5:-

u_i 0 0 =5. - -

.. _i.90cr =

=6 5

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I= m

. 8 0 =. _

a_.

-

g.80 fg *

.

: : cT 5 5 n^. m

x .70 5.:m 5

_3.70' "3.

= : -

uj. : :> .60 :._ _3 60 '

= :-

n- 5 i .

_ .50 ::.

,C .

:.50s .

h8 5 SDfULATE Group A at 83 Ir ches Icc-E A Test' Data Group A at 83 inches

_

i.40 : :.40 _ ;= :.

5_ .

. 30 E.. 3

-

*. . i.30

= *

5 i''

.20 E E.20'

: :

1 i.10 3 . j.10

*= =5 2

00"r.................... .............rrrr-...=.........=......... ....................i.009 .......... .

.0 10.0 20.0 30.0 40.0 50.0 . 60.0 70 0 80 0 80.0*

CORE HEIGHT (: 4 INCHES)

.

3/3/76-

. . _. _ _ _ _ __

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--

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C0liPRRISON OF Sit 10 LATE AND (1EASUREMENT IN RSSE!1BLY F-2CONTROL ROD ud.r;P A PT 15 INCHES- ' '

I! n3 -p . . .u.a .u .i ; .u i e a n .g.u. a. u .u u. p.u i ; . i i . i .u. p. i pi i i u . ' '-t * ' ' ' ' ' ' ' ' E

.E. E

l .C3 5. i

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a . l.EE

2 5; 1. L. 'l :- m

= :_,

l . 4 0 .=. _ {

:

E._

<

.g <

u.. }} | [. .m .

1.30 8. *-

n .i is

. :.

h*

f*,,. =-i ,g - -g

: ,ce a,t4J -.

. |E2 E *

o 1.10 : *: -Tfc. = == >r : m

. = = n (E 1.03 5.a

..! E 1.-

E nx = *- . coC 2h. 9 7 E.

.

u a-

w 5 E {> E B .

.80 2 '

E 1~

e- g- -;J -o . .

.3 a =.70 3 i E'w

cr- g- sn 5;560 SIFRILATE Group A at 45 Inches 5 ^

>

y. , .-3 .I,

. : IW X Test Data Group A at 45 Inches i 1.50 aif- -E .

.

:a Eu =

. 4 0 :r :- .:

hE \

/n. 3 0 E.

- ..: 73 : .<

5 E.,

20 dtr........ .............................'.I ii7..,,.'................... ...................E

. . .-

.0' 10.0 20.0 30.0 40.0 50 0 60.0 70.0 80 0 90.0a

CORE tiEIGtt f ( Iti ~IrictlES )- '

.

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- -___ _. - -- _. .--. - - . - .w. .

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COMPARISON OF SIMULATd ANC' MEASURENENT IN RSSEMBLY C-4CONTROL ROD GRCUP A RT 45 INCHES

1.10 pu. it u ..;................ ..... ......;..t.r...... ....... ...................;.........=- == =

1 60 $ iJ. .

. 5: 2::

1 50 ! 5E

.- 3. T-

E1 405. -

.E= x - ej Ej

'.

j1 . 3 0 E,. *,s~

5 I= -c

1.20 5.o: -. . .-

tsJ -3 ' i.:c 5 2-

1 10 E_.. . __ .r0 *

: *no_B i m '

a e: c

c ' 1.00 5. } E-- a. =

x- 5 i *-" .s3 5t.J , E

_5-*( '

5'> 5 i

[ 60 5'

i. _

a: 3-

g-

. ,-* a .=e'r' . .70 s. s

: :: u =:

:

. 60 5.. SIMULATE Group A at 4.'i Inches3 -

_5 .i-

2. I 1

3,

.bg 3. X Test Data Group A at .55 Inches ,g.

, ,

5 53 2.40 3. , .

.a3 5:a g,

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0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80 0 90.0. .

CORE 11EIGP" (IN' INCHES)

.

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9

COMPARIS0t10F SINULATE AND NEASURENErlT IN ASSEMBLY F-22 ff00RS AFTER RE fuRrt TO POWER

1 4 0 fu e i .u; e i i > > i_ | i i i i uu.i.p i i ut.u.s.;.us.uu.up.u > > i n.; i . = = a i p.u i.i i i ui i n's a a i t.u 1 4 0. :2 :2 -

-*

1 305. _it.30i .. N |

.

. .

31 201 203-

.. :a3 I

1 105. . 51 105- - 3

5. i' c

. 1 001 00 j. p-

: -

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90 ='

=x - _E.90..w1 5 . i m

: r. o : : oo

.80 : :.80 ca.:

2a 5 .:* :

.x - Us:

-* 3.x .70 : :.70'

:x 5 ..:: :

- w . . 6 C :. .5.60> 5 :.

. ~ , _.

5

:-

x 2 -

. _3.50a . 50 E.w E i . ,

'

SIMUL'TE Group A at 86 Inches !"'i A

A Test Data Group A' nt 85':'nches g.40.40 - .j .

=_ . i 'l .<

.30 5. .i. 3 0. ..~- ::- -

,

20 5. . f.20..-

- :-:.10 5- U .1'O

3-

i;=.

.

2 '

. 0 0 4 , , , , , , , , ,: , , , , , , , , , : , , , , , , , , , : , , , , , , , , ,: , , , , , , ,5 0 . 0rt m,,,,,,:,,,,,,,,,:,,,,,,,,,:,,,,,,,,,=.00 ;

0 10.0. 20.0 30.0 40 0 60.0 70 0 80.0 90.0,

CORE IfEIGilT f: N ItiCilES 1,.

| 3/3/76-

t

_ _ _ . _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ .- .,- g - , . >n

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C0tiPARISOft OF SIriULATE RtiD ME flSUREt1EttT IN AS'iEl1BLY C-42 tf0URS RFTER RE" URN TO POWER

'

l . /.9 Ag g g_gAgg gig e e e a e e e a e g_g e a e e a e e J,g a e e a e a Lt.2 g_Lg_g.g_3 J L Lg*,g_g ,tt,Lga,J J.,1 g a e a e a e e e J,g .LLs.t.e e e a a g e a a a e e a a a |_ t . 40: :

5 i

1.30 E 21 30 -

E , - i= =

:= ,

1.20= :1.20i5

~

^

5 i*

1 105. . . -_E1 10.'

E . 2 -..,= =

, =

t . 0 0 =E. -,

.

51.005 E.

x -=- =- =

to . 90 1 -- .-

-_E.90:-

33 -

o s i .?-

'

_s =.i.80 '2.60 i '

= na. 5 5 o

.70. : *

cr =.E.70:x: ->.

5 i*

*uj . = =

> .60 = _f.60-. : :

6- 5 I.

cr : :-

ia =. i.50.. . J O 2.' -.

,=

'

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Page 22: NSN no $.one YANKEE ATOMIC ELECTRIC COMPA Y 2 4 /w wg 9

N R C p r;'.+4 195 -(. u.s. NUCLE AR REGULATT.Y C . ilS$lON DOCKET NUM BE 7.

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"''" " '"NRC DISTRIBUTION r:R PART 00 DOCKET MATERIAL

To: F~ U.S.N.R.C. , FROM: Yankee Atomic Elec. Co. o^TE o' DeCuuENT

Westboro, Mass. 1 1 7A

W.P. Johnson DATE RECElVED

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Ltr. notarized 3-3-76...trans the following.. Additional information in gegard to ProposedChange # 125, Supplement 7 dated 2-19-76...

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(40 Cys. Received)_ . .. ..J. . . . . . - . _ . . _ .- . . . _ . . . _ . . .

ACENOWLEDGED. - . - - . - , . . . . , . n, ._ .

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PLA!TE NAME: Yankee Rowe

SAFETY FOR ACTION /INFORMATION ENVIRO SAB 3-8-76,

ASSIGNED AD : ASSIGNED AD :||.# BRANCH CHIEF : Purple W/6 BRANCH CHIEF :

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PROJECT MANAGER: PROJECT MANAGER :7EI~C. AS5~T. : Sheppard LIC. ASST. :

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