Text

Forwards marked-up Tech Specs,Indicating Addl Comments & Suggestions Re Reactor Trip Sys & ESF Instrumentation
	ML20090J314
Person / Time
Site:	Byron
Issue date:	07/19/1984
From:	Tramm T; COMMONWEALTH EDISON CO.
To:	Harold Denton; Office of Nuclear Reactor Regulation
References
	8936N, NUDOCS 8407300295
	Download: ML20090J314 (44)
	v • d • e

0 t

,e"N Commonwealth Edison

[

) 'One First N1tional Plaza. Chicago, Illinois g3 J Address Reply to. Post Office Box 767 4

v (j ' Chicago, Illinois 60690 July 19, 1984

. Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S.-Nuclear > Regulatory Commission Washington, DC 20555

Subject:

- Byron Generating Station Units 1 and 2 Technical Specifications NRC Docket Nos. 50-454 and 50-455 Reference (a):

December 16, 1983 memorandum from Cecil 0.

Thomas.

Dear Mr. Denton:

This is to provide additional comments and suggestions regarding the proof and review version of the Byron 1 Technical Specifications that was distributed in reference (a).

NRC review of the specific changes proposed here is necessary before the Technical Specifications can be finalized.

Attachments A through E to this letter contain marked-up pages of various sections of the Technical Specifications.

A summary explanation of the changes is provided for each attachment.

Justifications are provided where appropriate.

Some-of the changes address questions raised by. the NRC Staff in the review of changes previously proposed.

We understand that the NRC will review each of these proposed changes and

inform Commonwealth Edison of their acceptability.

Please direct any questions you may have regarding this matter

~ to this office.

One -signed original and fif teen copies of this letter and the attachments are provided for NRC review.

Very truly yours, f k fA-fb" T.R. Tramm Nuclear Licensing Administrator 1m cc:

Byron Resident Inspector 0

mens

+

8936N A

a.

~.

u-

. _w. w

.a.- a n ATTACIREM' A (Section 3/4.3)

- Circled items noted in this attactment have been previously sube.itted.

1) Table 3.3-2 (pg. 3/4 3-7) Reactor Trip System Instrumentation Response Times (RSB question 16).

Item 7 overtemperature AT response time should be changed from "5 4 seconds *" to "5 4 seconds *#".

Add the note to the bottom of the page "# thermal lag and RTD bypaa manifold delay time are not included."

This change is provided for clarification of what the overtemperature AT response time ird:ludes.

2) Table 3.3-3 (pg. 3/4 3-14) Engineered Safety Features Acta? tion System Instrumentation (RSB question 9).

To item 1.c. Containment Pressure - High - 1 add mode "4" to the applicable Modes column.

Table 4.3-2 (pg. 3/4 3-33) Engineered Safety Features Actuation System Instrumentation.

To item 1.c. Containment Pressure-High-1 add mode "4" to the " Modes for which surveillance is required" column.

This change is necessary because Automatic Safety Injection will occur in mode 4 on Containment Pressure - High - 1.

3) Table 3.3-3 (pg. 3/4 3-19) Engineered Safety Featutes Actuation System Instrumentation (RSB question 35).

Item 9.b. Reactor Trip, P-4 change the Total No. of channels from "2" to "4-2/ Train" change the channels to Trip from "2" to "2/ Train" change the minimum channels operable from "2" to "2/ Train".

i This change is provided for clari"ication. There is a total of 4 breakers with 2 breekers per train.

4) Table 3.3-5 (pg. 3/4 3-29, 30, 31 and 32) Engineered Safety Features I

Response Times (RSB question 17).

The Response Time Table has been updated and verified to be consistent with numbers used in the Safety Analysis. It is included in this package.

1

.==

x

- _ _ =

m._

it s

- ~ -

3 3

w

.i

-.2 s

I C

r f!

it

-w

]3 4 i.

3 t

u s

3

.?

3 3

3 4

y I

-r a

l E $

k 5 E E k

N N

l 3 n vt i

vi i s we i vs we i II g

32 i

. t i

l 3

W 2j' I

6 1

ll".

4. %

1

?

3 fe m

a A

-.4 M

IE k s

$.h 2,,

3 I s. Q f.

23

~

,i 5

.3 5

I C

2

- 4 s

)I

. I' 4 a

g "a

A 3

S.

gl g

-m w

l 4

g1 3

-t W.

h I

h i

ee-i I'

22 22 1 %

=.

5 A) 1 u

t 2

3 20 e

E a E.=a

4 5

.1 5

1 2

~1 1 2 2 3 up 9

t* Q eg,

" d, i t i r

=

43 3

u w

) g' yu

~ a, 2

s o

v "2

84 3

.t 4.=

g w

i E

u% u%

5 3A

$=S gI k

u 3' & & e5 u

i

.5

.3 2 ?p 4

A J u as$5

$;aA t

YR SAYON - 13 TIT 1 3/4 3-7

. \\ u. : 8..

6 J

,7-.

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

t i

, ~, - + -, -, - ~, +

. = = = =.

I f000f 5 MY COM

(-

b 5

s:

h Ch h

a s

41 r

A A

.,c M.

3 4

4 e

h 44 4

4 4

4 l

y "h

a4 a

a J

z.a 1

g i

1_

i

~

6 g

2 i

~

=

~ ~

~

e 6

s

=

4 a

a 2

I g.

II pl g

du k

a g

_a t

s M

8'*

]

w p

"' l g

3 e -

g y

g g=

1 3

3 4

e

~

t-5 J.

s 3

k gg i.

l D

! l j:i.la.

gg m

g 3

r 3_.!

--h S, a!!

H,.

_I.

u_

s2 e

...53.. v.-

i 1..,

8 2E_3 1.!3 35 21,53 g

33,.3 3, s'

- ~

3

=

w, n.

44 em j!

n 3 et s-33333 4

.d d

4 4

$4 4

d guns

3. a

.~

sneu - untT L L/4 3-14

,. L iy.:w. <

. _.~

I

...J

2.

_. c.. _.. :

i 300f $ NN 'M zig m

aa

=

as a

a

5=

a4 4

4 4

44 a

i I S I-1 1-a.

3

,#< p -<g 2x-ie i

s i

ae

=

e i

$.$.g

.a

.m I

4 15m sE s

i s

iE a

33 E

=-

i a

3 sg 4

=-

j k3 55 5-b

$5 2

i s.

N 2E55%

4 4

T,3

42%*

.d s

s i

=s s

I l

g E~c i4 i4

$, #;_)

2twk-

==

z z

z

==

=

g

.2g i

44

~

44

~

3

.3 4*

4

=

3

.i

. t. <.

3

=i

.5 2.3_2"d s s

-g wa ! 4

.t.a w -

t 5

s Qr '

4a. a t.

i.

a --

=f.

2

1, 3

? > 2. 1 1 u

g..

=.

a.

wAe * **

8.

M $ = $$

-l

. 2. u !.. $ $

a.

s.

5 i

. 2 5

5

,k $.k h.

e

-e 8

.==

J 8

N

}A y ! E" 1EEN $f i

.f ggg 4

- - hm! $3 ? O

3. *3 :. 2. M. u! f ** !

W T.

\\

1 i 1 ?'

E-

=

<-=w-

=

u-

-.22

~

Tdt 0N - WC L 3/ 4 3-32 IO.

\\

~

O O

O

~

tc 1.

TABLE 3.3-3 (Continued)

,y y

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION e

ol E

HININUM 4

TOTAL NO.

CHANNELS CHANNELS APPLICA8LE l

+

e FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE N00ES ACTION 9.

Engineered Safety Features Actuation System Interlocks a.

Pressurizer Pressure, 3

2 2

1, 2, 3 20 P-11 b.

Reactor Trip, P-4

% 2/T. ain 2/Trcan 2/ Train 1, 2, 3 22 Low-Low T,yg, P-12 4

2 3

1,2,3 20 c.

W g'

D d.

Steam Generator Water Level, ts.

2/sta. gen.

2/sta.

1, 2, 3 20 y

P-14 (High-H10h) gen.

In any gen. In g

operating each i

,.i sta. gen.

operating sts. gen.

4

~

3 es I

c.s Y

i n.

i

no i

%m l

m e

u c3 l

'l 1

e.

_r I

G

~

l

'.D i

x

. P!l00F & REYlEW C9R TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 1.

Manual Initiation a.

Safety Injection (ECCS)

N.A.

i b.

Containment Spray N.A.

c.

Phase "A" Isola'tfon N.A.

d.

Phase "B" Isolation N.A.

e.

Containment Vent Isolation N.A.

f.

Steam Line Isolation N. A.

f.

Feedwater Isolation N.A.

L h.

Auxiliary Feedwater N.A.

1 j

i.

Essential Service Water N.A.

j j

Containment Cooling Fans N.A.

1 k.

Start Diesel Generator N.A.

I 2.

Containment Pressure-Hich-1 a.

Safety Injection (ECCS) i 27(1)/12(2) 1)

Reactor Trip i2 i

2)

Feedwater Isolation

< 7(3) 0.)

m

,,1 2-L 3)

Phase "A" Isolation

' ' ' ~ " '

ir 7 l,

m

<as 4)

Containment Vent Isolation im j

5)

Auxiliary Feedwater i 60 Aj {(4

i

.6)

Essential Service Water

< &(91';;/'-'

/'4 O) a f, s

,s l

7)

Containment Cooling Fans i n '-'/?0"'

MO 8)

Start Diesel Generator i 30 12.

'3.

Pressurizer Pressure-Low

?

a.

Safety Infection (ECCS) 1 27(1)/12(2)

L 1)

Reactor Trip i2 7(3) 2)

Feedwater Isolation 1(*)

U 3)

Phase "A" Isolation

< a, - - '/ 2 7 ' ' '

r,1 4)

Containment Vent Isolation i 25 7

,j 5)

Auxiliary Feedwater i 60 0) m r1 6)

Essential Service Water i +;

, a-) y 2.gy 7)

Containment Cooling Fans 1 59 f)

^10 8)

Start Diesel Generator

_ 20: 12 BYRON - UNIT 1 3/4 3-29 9

=

- =

e

.ua -

.a

... t _ _ -

._...____u.

...., r.

^-

f P

PROCF & REVGf TABLE 3.3-5 (Continued)

L ENGINEERED SAFETY FEATURES RESPONSE TIMES j

INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECON05 1

4.

Steam Line Pressure-Low j

f a.

Safety Injection (ECCS) 1 22(4)/12(5) 1)

Reactor Trip i2 2)

Feedbater Isolation 1 7(3) g)

< i '"/.;

2-

~

l8 3)

Phase "A" Isolation l

~

4)

Containment Vent Isolation i 25 n _e'-) 7 r

to 1

5)

Auxiliary Feedwater 1 60

(,)

6)

Essential Service Water

(

-/ ", r"-) 4 2.

i 1

fn W

7)

Containment Cooling Fans 1 95

'c ' -) 4 0 f'

8)

Start Diesel Generator i te 12.

b.

Steam Line Isolation 1+

7 5.

Containment Pressure-Hich-3 g

in j.

a.

Containment Spray i E(n y

m:'

b.

Phase "B" Isolation 1'

-) 21 !

g I

6.

Steam Generator Water level-Hich-High i'U a.

Turbine Trip i 2.5 b.

Feedwater Isolation i 7(3) i F

7.

Steam Generator Water Level-Low-Low I

a.

Motor-Oriven Auxiliary Feedwater Pump i 60 b.

Diesel-Oriven Auxiliary Feedwater Pumps 1 60

).

8.

Containment Pressure-High-2 f

Steam Line Isolation 17 f

9.

RWST Level-Low-Low Coincident with Safety Injection M

Automatic Opening of Containment i ^~(21 __: /00 Sump Suction Isolation Valves Y

BYROM - UNIT 1 3/4 3-30 3

D

,,,,-.-.,,,-.,...,,__.-n,.

-._,-._.,n_

=.

I l 900F & REV1EW COPY

~

TABLE 3.3-5 (Continued)

ENGINEERED SAFETY FEATURES RESPONSE TIMES I

INITIATING SIGNAL' AND FUNCTION RESPONSE TIME IN SECONOS 10.

Undervoltace RCP Bus i

a.

Motor-Oriven Auxiliary Feedwater Pump i 60

?

b.

Diesel-Driven Auxilf ary Feedwater Pump 1-ti bo

)

11. Division 11ESF Bus Undervoltage Motor-Oriven Auxiliary Feedwater Pump i 60

12. Loss of Power ESF Bus Undervoltage (CkP-r ; '. _...J L.'. '.-% 14 l 9 a.

MM Grid Degraded Voltage ';..

>me newy.ny';

9 3goe 30 l

b.

j 13.

Steam Line Pressure - Negative Rate-Hich { g, 4 p gy Steam Line Isolation 17' 14.

Phase "A" Isolation r

Containment Vent Isolation i+7 1

15. Auxiliary Feedwater Pump Suction Pressure-Low-Low 1

Autmatic Switchover to ESW N.A.

!i l

7 l

4

.t i

i h

'l I

BYRON - UNIT 1 3/4 3-31 9

i

_,.-..:..__ -- L'::

1-....

._..L..--

l,.*

{

F hpfhhff T/EsLE 3.3-5 (Continued)

L i

TABLE N01 ATIONS (1) Of esel generator starting and sequence loading. delays included.

(2) Diesel generator starting and sequence loading delay not included.

Offsite power available.

Hydmlu.

(3) -A4e operated valves.

l l

(4) Diesel generator starting and sequence loading delay included. -RHR l

7. aet: .~;uu.u. Only cenMQ41 c%iw3 pumps inci,ded, t

i (5) Diesel generator starting and sequence loading delays not included.

Offsite power available.

""" ~

c

4 -c Mdri only cen M Fveft Ckqing MPs ihcluds.d.

(")

fr-" ~ ~ de hj;.;;..,' d;d.

i (G) Doe.s not include, vglVe closur4 tim e.

t 1

.J i

li 5

e

!l l

1'l SYRON - UNIT 1 3/4 3-32 9

~-

a.__._m._.__._

l l

ATTAC15 EDIT B (Section 3/4.4)

Circled items noted in this attachment have been previously submitted.

I i

l 1)_ Section 3.4.1.2 and 4.4.1.2.3 Reactor Coolant System (pg. 3/4 4-2) RSB question 28).

Change the first line of the LCO to read "At least three of the reactor coolant loops listed below shall be OPERABLE and at least two of these

?

reactor coolant loops shall be in operation:*".

l Change Action statement "b" to.*c".

L L

Add Action statement b as follous-

"b.

With only one reactor coolant loop in operation, restore at least two 4-J

{

loops to operation within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SitFFD0hBI within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ."

l:

}

Change Surveillance Requirement 4.4.1.2.3 to read "At least two reactor j

coolan6 loops..."

These changes are necessary because in mode 3, the coactor coolant loops provide sufficient heat removal capability for removing decay heat. Two 4

loope must be in operation to meet the DtB design basis when considering i

an inadvertent control cod withdrahal event from subcritical. Single p

failure considerations require that three loops be operable.

1 i

i l.

2) Section 3.4.1.3 Reactor Coolant System (pg. 3/4 4-3) (RSB question 1).

1 In note ** at the bottom of the page change "380*F" to 350*F".

1 L

This change is necessary to maintain consistency with revised Tech Spec 3.4.9.3 also in this package.

y

]

3). Section 3.4.1.4.1 (pg. 3/4 4-5) (RSB question 1).

In note M at the bottom of the page change "380*F" to "350*F".

l.

This change is necessary to maintain consistency with revised Txh Spec j

3.4.9.3 also in this package.

i

4) Section 3.4.4 Relief Valves (pg. 3/4 4-10) (RSB question 5).

)

Delete the Action statements and replace with Insert "A" which reads as j

'follows:

l L

"ACTIObl:

l y

With one or more WORV(s) inoperable because of excessive seat i,

a.

leakage, within 1 hout either restore the PORV(s) to OPERABLE status or close the associated block valve (s); otherwise be in at least HOT STADEBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWhl within the following 30

hours, i

.=

=

. =

=

z._ _

3,33;; ;,

.__.a__

l

(

b.

With one PORV inoperable due to causes other than excessive seat l

leakage, within i hout either testote the PORV to OPERABLE status or l

close the associated block valve and comove power from the block valve: restore the PORV to OPERABLE status within the following 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STAh0BY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD S M DOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With both PORV(s) inoperable due to causes other than excessive seat c.

leakage, within 1 hout either testore each of the PORV(s) to OPERABLE status oc close thwit associated block valve (s) and remove power from the block valve (s) and be in HOT STAbOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and i

COLD SIRFrDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

l d.

With one or more block valve (s) inoperable, within I hout:

1) restore the block valve (s) to OPERABLE status, or close the block l

valve (s) and remove powet from the block valve (s), or close the PORV and remove power its associated solenoid valve: and 2) apply the ACTION of b or c above, as appropriate for the isolated PORV(s).

The provisions of Specification 'J.O.4 are not applicable."

e.

This change is necessary so that the Pressurizer PORVs are not removed from service for an indefinite period. The revised Action statement is consistent with assumptions in the FSAR.

i

5) Section 3.4.9.3 Overptessure Protection Systems (pg. 3/4 4-35 and 3/4 4-37)

(BSB question 1).

For Tech Spec 3.4.9.3 delete the 140, Applicability, Action Statement and Surveillance Requirements and replace with the new attached pages 3/4 4-35 f

and 3/4 4-37.

The revised Tech Spec will read as follows:

f

==cTOR coouwr STSTEn t

{

j OVERP m N P90fBCTICU SYSTEMS LTmITING e m nITION FOR OPERATION 3.4.9.3 At least one of the following Overptessure Protection Systems shall be l.

OPERABLE:

I Ttso residual heat removal (RHR) suction relief valves each with a a.

Setpoint of 450 psig i 1% or I

)

b.

Two power-operated relief valves (PORVs) with lift Setpoints that vary with RCS temperatute which do not exceed the limit established I

in Figure 3.4-4, or The Reactor Coolant System (RCS) deptessurized with an RCS vent of h

c.

j greater than oc equal to 2 squate inches.

APPLICABILITY:

MODES 4 and 5, and MODE 6 with the reactor vessel head on.

l h

-. ~

z=

x -. - = :-

..-. :. c

_.;. a.-

>v_=-

l ACTION:

With one PORV and one RHE suction relief valve inoperable, eithec a.

restore two PORVs oc two RHR suction telief valves to OPERABLE status I

within 7 days oc depressurize and vent the RCS through at least a 2 l

squate inch vent within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

b.

With both PORVs and both RIEt suction relief valves inoperable,

.depressurize and vont the BCS through at least a 2 square inch vent L

within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

a k

In the event the PORVs, oc the RI5t suction relief valves, oc the BCS c.

4 vent (s) are used to mitigate an BCS pressure transient, a special Report shall be prepared and submitted to the Commission pursuant to i

Specification 6.7.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs, oc the RIEL suction relief valves, or RCS vent (s) on the transient, and any corrective action necessary to prevent recutrence.

d.

The provisions of Specification 3.0.4 are not applicable.

l asact0E C00u we SisT u b

g- ;-vi i mw r omnyin=="r5 4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by:

Petformance of an ANALOG CHAbEIEL OPERATIONAL TEST on the PORV a.

actuation channel, but excluding valve operation, within 31 days prior to entering a condition in which the PORV is required OPERABLE and at least once per 31 days thereaftet when the PORV is required OPERABLE:

b.

Petformance of a CHARRIEL CALIBRATI0tl on the POEV actuation channel at least once 18 months; and Verifying the POEV isolation valve is open at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months c.

when the PORY is being used for overpressure protection.

t 4.4.9.3.2 Each RHE suction relief valve shall be demonstrated OPERABLE when the Rigt suction relief valves are being used fot cold overpressure protection as follows:

l a.

For HI5t suction relief valve 8708B:

1)'

By vocifying at least once per 31 days that RHE BCS Suction Isolation valve IRH8702A is open with power to the valve operator removed, and 2)

By verifying at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months that 1RH8702B is open.

b.

For Rigt suction relief valve 8708A:

t By verifying at least once per 31 days that IRH8701B is open 1) with power to the valve operatot removed, and 2)

By verifying at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months that 1RH8701A is open.

9

.. =

2 : T z _ _.

33_

^

1 Testing pursuant to Specification 4.0.5.

c.

t 4.4.9.3.3 The RCS vent (s) shall be verified to be open at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

when the vent (s) is being used for overpressute protection.

Except when the vent pathway is provided with a valve which is locked, sealed, or otherwise secured in the open position then verify these valves open at least orce per 3L days."

This change is necessary to include the RHR suction relief valves in the Overpressure Protection Systems and to delete the requirement that the overpressure Protection Systems be OPERABLE in mode 3 when the temperature of any BCS cold leg is less than or equal to 380*F.

The pressurizer PORVs and the cold overpressute Protection System are not required for dealing with overpressure transients when the primary temperature is above 37.n*?.

This is because at 350*F the Appendix G 11mit is more than 500 psi above the pressurizer safety valves opening setpoint of 2485 psig and this macgin becornos greater with increasing primary temperatures. Hence the safety valves will prevent pressure transients from exceoding the Appendix G limits when the primacy temperatute is above 350*F.

6) BASES Section 3/4.4.1 Reactor Coolant loops and Coolant Circulation (pg. B 3/4 4-1) (RSB questions 28 and 1).

j Change the second paragraph of the Bases to read as follows:

"In Mode 3 two Reactor Coolant Loops provide sufficient heat removal capability for-tenoving decay heat; however, single failute.

~

considerations require that three loops be OPERABLE."

This change is necessary to maintain consistency with revised Tech Spec 3.4.1.2.

I In the last paragraph, second sentence change "380*F" to "350*F".

s i

t This change is necessary to maintain consistency with revised Tech Spec 3.4.9.2 also in this package.

1) BASES Section 3/4.4.9 Pressure Temperature Limits (pg. B 3/4 4-19) (RSB question 1).

l In the second paragraph first line aftet. The Operability of two PORVs add

oc two Bl5t suction valves,".

l 1

l In the same paragraph change "380*F" to "350*F".

i Add the following as the last paragraph to Bases Section 3/4.4.9 "RHR RCS

}

suction isolation valves 8701A and 8702A are interlocked with an "A" train i

wide range pressure transmitter and valves 8701B and 8702B are interlocked with a "B" train wide tange pressure transmitter. Removing powet from valves 8701B and 8702A, prevents a single failure from inadvertently isolating both R15t suction relief valves while maintaining RHR isolation 4 capability for both RHR flow paths."

This change is necessary to update the bases consistent with the revised l

Tech Spec 3.4.9.3.

9

---.-..-----.z.,--.--,~,.

n C

IN, j

PR W & g g y y p.7,

ww m"r m w e

me n-w A

b o

!.J.m i us C::NOI'*TCN FJR CPGAT*CN c

^

V o

-th re4.

4.t,. } $

L4.,L2.At least me ofpm nec.ar =notant toons listad metow snail l

.e C aA u and at i.ast.

of wese mac.e oiant ico man e in 4 ~g a c e

r.e -

}.a. s- {a-d a.

Reestor Caelant Laos A and its associated stams generstar and r

m.c::or s1.pt

t. g.2 5.

Reestae Cholarrt f.aos I and its associated staas generstar and (f

i.23C e

reester-coolant pues,

[# W Eh 4 { *I g{

. c.

Reestor Caolant Laos C ts associated stans generstar and reactor coolant psmo, e

sg d.

Anestor Caetant f ass 3 and its asacciated staan generstar and oI reactor coolant pump.

4 :t:

9 c

A P _ICA8I!.ITY: MODE 3.

gg-3.S d

' ~

o 3

.ASUElb Wtn less taan t e aseve mouired reactor =ciant lecos CPGA8LE, j

a.

[

restare us recoired loans to CPGA8LE status wit.Mn 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or to in M S'AI17.CWN viJtin tse next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

I..

W:n no reactar enolant loss in operation, suspend all ooarst!ons

c..M involving a recussion instorga concent:stion of =a Reactar Caciant Systas and inesiately initiata car =ective acMon to return tne resp 41 red Mec*De c3 1 apt 1oso 13 ogerstion.

s SUN RED 1JLwr ia i

At least the aseve recuired reactar coolant pueos, if not in

4. 4. L 2.1 j '

oserstion, sasil be determined CPGASLI onca per 7 days my verifying cor-oct

(.-

3reaker aligneumts and inetcated poner availasility.

The reeBired stam iJ-_.Lu. a $nall be cetarWined CPSASLE ty 4.4.1 2.2 verifying seconmary side nar-ow range wear level ts te grestar taan or soual

.i to 45 at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

two s

At least aan reactor coolant loser sna11 te verified in ooerstion

4. 4. L2. 3 and circulating reactor coolant at feest onca per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

e-4 w.ar.aolant nueos say te sceneryftsd der us.a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 2Mwicad-

=M1 (1) no coerstions are penittad tnat wuld cause citution of ce Meactsr Caetant Systaa toren -

.s en, and (2) core outlet tammersture is 4

saintained at least ic*? below saturstion tancerature.

1 3/' 4*1 I<s*

SYW2M - UNIT l' I,9

~

aS4

.~

z * -, -.

^

em.*

-m.

--w-.-v---mw.---m

,.y me-y-

g+ww--y

,w-

,ww.m.--,

-e&

g,-,

,,-y-

vry99wy.-.-gT-g--wpqiw-y-r--r c e d w e-

! +.

+

u o

a.

l

.1 m. -...

....s.......L.,

v RDCTOR CCCLANT SYSTE9 hkg

[ QL]*

8 I

HQT_.9AfD_CWM

.LD8tTT?tG CCNOI*TCM 20R OP8RATICN

~

3.4.1.3 At least two of ue locos listed below saall to CPGA8LE and at least one of these locos saall se in coerstion:8 a.

Reactor Coolant Laos A and its associatad steen generstar and reactor

[

coolant p m,"",

3.

Reactor Caolant-Laos 3 and its associated staan generstar and nectar coolant pumo,"

l f

c.

Reactor Caelant Laos C and its associatad staan ;-

.s.or and n. actor I

coolant puas,**

d.

Reactor Caolant Laco.D and its associatad staas generator and reactar

)

l coolant p m,""

8 e

a.

MR Laos A, and/ep f

f.

EI laos I.

l AP#LICA8ILITY: MCCE 4.

3 l

P l

ACTION:

( l

' dita less can tae aeove naufnd nectar c=clant and/or RHR locc4) i a.

l

' OPGA8LE, imediata)y initiata come.1ve action ta return tae mquind locos ts CPGA8LE status as seen as possihte; if me i

remaining OPGA8LE loon is an RHR loco, to in CCL3 SHLJTUChN witain i

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

1 3.

' dita no reactar enolant or RHR loco in eserstion, suscend all i

coarations invahing a nduction in boren =sacantntion of' ce Reactor Coolant Systas and imentataly initiata cornetive action is s

return the requind coolant loco to onention.

t i

2 j

"All reactar coolant pumas and RHR pumos say be cannergitad for un ts 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months l

1 provided:

('.) no coerstions a.M persittad taat would cause 211ution :f : e teactor Caolant Systas moren :sncantrstien, and (2) este outlet tancersture 1s saintained at least IC*F below saturation tammersture.

""A reactor coolant puso snail not be started vita one or sort of tae Reactor Coolant System :sid leg tamoemtures less taan or ecual to 3802' unless t.e secondary wetar tammeraturn of esca staan generstar is less taan SC*F accve l

essa of tas Reactsr Coolant Sysas esid leg tanneraturss.

35 o'f a

L SYRCN - tjNIT 1 3/a a-3 I.l' 1 A,_

l

\\

u.._

u __

.. _.. ~ -

...u :. _..

_- a.

FPSF& REyrgy ggpy i Ro crea C:c uNr sYsr e CCt.D SHUTDOWN

LCOPS FT1.J.3 LIMITTNG CONDITTCM FCR OP EATTCH

3. 4. L 4.1 At least one residual heat removal ('HR) Toop shall be CPGASLE and in operatierr, and eitner:

a 4

a.

One additional MfR loop shall be CPGA8Li#, or 3.

The secondarf side narras range water level of at least two staae generators sna11 be grestar man 43.

f i

AP'UCA8TUTY-MDE $ with reestar coolant loops filleeff.

M:

4 Wi*.tt one of the RHR loops inocerania and with less than ue required a.

stems g

..i r level, immediataly initiata car-octive action tm return tne ineooracle RHN loco to CPGA8LE status or restart t.w required stamm generator level as soon as possible.

b.

Wita no RHR loop in operation, sussend all coerstions involving a 2

. 4 r.i. ion in baron concentration of *.no Reactar Caolant Systas and isseeiately initiata corrective action to return.no esquired RHR loop te operation.

s I

SURVEILUNCE RECUI2fMENTS The sacandaef side water level of at least two staan generstars

4. 4. L 4.L1 when required shall be datarained ta te witain limits at least onca per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4. 4. L 4. L 2 At least one RHR loco shall be dotarsined to be in coeration and circulating reactar coolant at least ones per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

"The RHR pass say be doenergi:sd for un to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months provicad: (1) no acerstions are perinittad tnat would causa dilution of the Reac*.or Coolant Systas baron l

concentration, and (2) core outlet tamperature is saintained at least 10*F below saturstion tammersture.

imne RHR loco say be inocerante for um to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillanca tasting proviced the otner RHR loop is OPEA8LE and in coaration.

90A reactar can1 ant puno snali not be star *ad with one or acre of the Reactar Caolant Systas cald Ir.g tanceratures less t*:an r equal ts 33087 unless the seconeary watar tannerature of esca staan generater is less taan 50*? anove eacn of the Reactor C.solant Systas en1d leg tancerstures.

35o F r(

d 3YRON - UNIT 1 3/4 4-5

.. ~.. p.mm, ;

~_

..,m

.._.,.,,w.,.

. - - -,,,.y_e,

,,,,,%wc,-----.,-,-----,,m.,

--e--

m

.am__

3 1

' O.

F~

h

h. f h f f

1. UW

)

~ I/A. 4. 4 REUT* VAL.VE5 g

~

LLMmNG C:7.4mCN FOR CPTRATICN 3.4.4 All power-enerstad relief valves (PCRVs) and their associatad 34ccx -

O valves small be OPERA 8 M.

APeU CA8IU Tf: MIDES 1, 2, and 3.

O.

gep)4c<,, wiR W N O

nta one or een PoRV(s) inogenste, wiuin i neur eine ore }

PORV(s) to CPERA8Li status or close us assoc 1 olock I

-valv and remove somer frse ce niccx valv

ocerwise. to in at least - -

. AM08Y wicin ce next 5 n and in C::L3 SHUTCC'nN within :ne fel 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

O t

witri one or sere nioca ve inocereale, wicin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months eicer.

I restore the 31oct valv to -

L1 status or close tne blocx valve (s) and. _

J ;r free ce act valve (s) or close me PC L.

and remove t'

==41 pomer-ocenis to in at least HQT STANO witnin

next. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in C:L2 SHLITU wicin== following I,

30 3

I i a

- a--:r: = : = m -- - = t e rt:.

~

w p

SURVEILLANCE 4tCube,EsT3

4. 4. 4.1 In assition to the recuimmenta of Soecification 4.0.5, eaca PCRV shall be demonstrated CPERAtu at least once per la montas by:

a.

Perforeence of a C4 ANNE!. CAU3 RAT *.QN,, and n.

operating ne valve tareuen one commteta cycle of full travet.

O 4.4.4.2 Eacs $1ock valve shall ne demonstratae CPERA83 at least onca ser 92 days by coersting sne valve tarougn one czeleta cycle of full t.avel unless j

ne Diock valve is closed wita power rimaved in orcer to meet tae -equineents of ACTION a. of Specification 3.4.4 j

i: O 7..

, 3 l

f

.<===..w.4.

.w-.

.=..w m a a

..-.-..y

...... ny

.I,,

j

_ vi.

f 0,........,

-..--s=

a -

TI0^- -/;I; 2' H ' ' * -^ ~

T O

i SYMON - UNIT 1

, 3/ 4 4-10 o

g vi i

l

. a a x --

L Ser-I-ACTION:

With one or more PORV(s) inoperable because of excessive seat a.

leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the FORV(s) to OPEM.BLE status or close the associated block valve (s); otherwise be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With one PORY inoperable due to causes other than excessive seat leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV to OPERABLE status or close the associated block valve and remove power from the block valve; restore the FORY to OPERA 3LE status within the following 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT,, STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With both PORY(s). inoperable due to causes other than excessive c.

seat leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore each of the PORV(s) co OPERABLE status or close their associated block valve (s) and remove power from the block valve (s) and be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

j t

d.

With one or more block valve (s) inoperable, within 1 hour:

1) restore the block valve (s) to OPERABLE status, or close the block valve (s) and remove power from the block valve (s), or l

close the PORY and remove power from its associated solenoid valve; and 2) apply the ACTION of b or e above, as appropriate

{

for the isolated PORV(s).

The provisions of Specification 3.0.4 are not applicable.

3 e.

l I

j j

t

?

I 9

3M pyp (L6fLAC.C MWN N

~N s

agAc-':R c::ct. ANT SYW o

spet35 TNT 8'C"N UN hhhf k i._%,, i ;,

ONor"*CN t':R tPU.A7*CM

3. 4. 3. 3 At least e of me following Cversressure 7

.ica Systans sna h

)

., \\;@ W w % <M A

's'*IS te CMilASLL a.

7=e m tilst valves UCRVs) 12

.ni et vary wiu RC3 -

esture as snamn on ~ quee 3.4-4, :P 3.

The Reer".ar Iant yttan (TC3) ' ressuritat wit 3 an Q,ent of

)

f ncies.

greater

c equal *4 1 1 i

re f any C : sic leg is less man AiHN.ICA8!L'""Y: ME wnen tae -

e u :. m.a=r,.s,.s n..a an.

ar an.u w.3 s and a n U

g:

a.

' dita one f

le, eitne mstsre ce incoersale MRV u CM!lAetl s.atus wi-in 7 days se ressurita and vent ce ACE througn at least I se inct v wiuin== next 4 acurs.

i

(

)-

3.

'41ta acts M inasarante, tuoressuri sne vent ::e RC3 ureugn at least a 1 inct vent vicin 3..cu c.

Lt the eitner tSe MRVs or ce AC3 e (s) are und to titigata an RC3 sure transient, a Scacial Reser. s.

11 :s :rscarse ana suoni.at ta tae *Mssion ;ursuant u Scecif.

tce i.7.Z wi21n

.The r1oort snall cascrite me ci-t.=ss-initiating me

)

30 s.

y 1ent, ce ef"tst of me PCRVs se RC3 vent (s) n me trsnsient, any car-esttve action,ecassary u :rivens mcu N Wsicas of Soecification 3.3.4 art not asolican l

8 I

m I

(

1 ur a-is

, me,.,mr t

)

!) ' /

~_

...w w a

REACTOR COOUWT SYSTEM OVERPRESSURE PROTECTI0tt SYSTEIE LIMITING C0tBITI0li FOR OPERATIOli 3.4.9.3 At least one of the following Overptessure Protection Systems shall be OPERABLE.

a.

Two tesidual heat removal (RHR) suction relief valves each with a Setpoint of 450 psig i 1% or b.

Two power-operated relief valves (PORVs) with lift Setpoints that vary with BCS temperatute which do not exceed the limit established in Figurg 3.4-4, or The Reactor Coolant System (BCS) depressurized with an RCS vent of c.

greater than or equal to 2 square inches.

I APPLICABILITY: MODES 4 and 5, and MODE 6 with the reactot vessel head on.

i ACTIoli:

a.

With one PORV and one RHR suction relief valve inopetable, either f

restore two PORVs oc two HHR suction relief valves to OPERABLE status within 7 days or depressurize and vent the RCS through at least a 2 square inch vent within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

i l

b.

With both PORVs and both RHR suction relief valves inoperable, depressurize and vent the BCS through at least a 2 squate inch vent within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

c.

In the event the PORVs, oc the RHR suction relief valves, or the RCS L

vent (s) are used to mitigate an RCS pressure transient, a Special i

Repott shall be prepared and submitted to the Commission pursuant to Specification 6.7.2 within 30 days. The repott shall describe the circumstances initiating the transient, the effect of the PORVs, or the RHR suction relief valves, or RCS vent (s) on the transient, and any corrective action necessary to prevent recurrence.

d.

The provisions of Specification 3.0.4 are not applicable.

l 3/4 4-35 BYR0ti - 13i1T 1 l

-~

.:. : o k - =. a. ;

_ =._

. ~

=.... _.

h..

DELETE AruD vtEPt AG WT1+ NELJ PAGE 3/4 4-37 y

i$hhfhinhfbY'bbi

1. UN suRveb cs emen 7

70RV shall be demonstrated CPGMiG ty-j 4.4.S.3.1

on me PCRV a.

Periw. __ ~+ of an ANAUTs CHANNEL CPGATICNAt.

i actaation I, but excluding valve ocerat

, wi cin 31 days d

prior to ng a condition in wtica ce is aucui-ed OPGA8LE arut at least per 31 days taereaftar ce PCRV is required CPGASLn; l

3.

Perfemance of a CALI3RA c on us aCRV actuation enamsel at least once per la

and

{'.

4 c.

Verifying ce PORY isolati alve is ocen at least ones per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months unen the PCRV is being overgressure protaction.

1 4.4.S.3.2; The RC3 vent (s) s be verifiet be coen at least once per

.O 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months " wwmi tne vent (s) i seing used for av ressure prataction.

i l

I i,. l l

pc 16 locxed, sealed, "zcast weeg/ue vent patamey is provided vita a valve weica i e

k or vi;...V.e secured in us coen position, con verf?/ *. nase va ves ocen at least per 31 days.

i, I%

1 4

i 1

1 ll g*

q.

ll a

l!

,, l SY1ut - UNIT 1 3/4 4-37 b

a-

- ~ -

r--y w-ww e

ye,w

++-ww.y..w--

w

-,,--*-,v

...- -.~ - -

REAC'!OR COOLANT SYSTEM i

i SURVEILLANCE REQUIREMENTS i

4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by:

a.

Petformance of an ANA14G CHA W EL OPERATIONAL TEST on the PORV actuation channel, but excluding valve operation, within 31 days ptiot to entering a condition in which the PORV is required OPERABLE and at least once per 31 days thereafter when the PORV is required OPERABLE:

b.

Performance of a CHAMEL CALIBRATION on the PORV actuation channel at least once per 18 months; and Verifying the PORV isolation valve is open at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

{

c.

when the PORV is being uced for overpressure protection.

i.

4.4.9.3.2 Each RHR suction relief valve shall be demonstrated OPERABLE when

}

the RHR suction relief valves are being used for cold overpressure protection as follows:

- a.

For RHR suction relief valve 8708B:

I 1)

By verifying at least once per 31 days that BHR RCS Suction f

Isolation valve IRH8702A is open with power to the valve j

operator removed, and 1

2)

By verifying at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months that 1RH8702B is open.

b.

For RHR suction relief valve 8708A:

1)

By verifying at least once per 31 days that 1RH8701B is open with power to the valve operatot removed, and 2)

By verifying at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months that IRH8701A is open.

c.

Testing pursuant to specification 4.0.5.

4.4.9.3.3 The RCS vent (s) shall be verified to be open at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

when the vent (s) is being used for overptessure protection.

g t

i

Except when the vent pathway is provided with a valve which is locked, sealed, oc otherwise secuted in the open position, then verify these valves open at least once per 31 days.

3/4 4-37 BYRON - UNIT 1

^

)

3/4.4 REACTOR-t00t. ANT SY$794 i.

BASES i

j 3/4.4.1 REACTOR COGLANT t. COPS ANO C001. ANT CIRCU!.ATION

)

i 1

The plant i designed to rate with all reactor coolant locos in operation

)

and enintain DN8 i r i "* ring all nomal operations and anticipataa DES 1 a[ with one reactor coolant loco not in operation

{

transients.

In 1

W= enecification. 5 that the plant be in at least HOT STAN08Y witnin X house.

NA 6 ova s w d' A N u u M 4

s

+wa r**Gr'Y 4 "

Y " ' D " 8 A In MODE 3, W reactor coolant loop 5 provide [ sufficient heat removal d

capability for removing decay heat; however, single failure considerations 4

require that w loops be OPERA 81.E.

Mr et In MIDE 4, and in MODE 5 with reactor coolant locos filled, a single reactor coolant loop or RHR loop provides sufficien+. heat removal cananility for removing decay heat; but single failure consicerations require that at least two loops (either RHR or RCS) be OPERA 81.E.

In MODE 5 with reactor coolant loops not filled, a single RNA loop provides j

sufficient heat removal capability for removing decay heat; but single failure 1-considerations, and the unavailability of the staan generators as a heat j

removing component, require that at least two RHR loops be OPERA 81.E.

i The operation of one reactor coolant pump (RCP) or one RHR p ep providas

~.

adequate flow ta ensure sixing, prevent stratification and produce gradual

(

reactivity changes during boren concentration reduc *. ions in the Reactor Coolant Systas. The reactivity change rata associated with baron reduction will, l

therefore, be within the capnility of operator recognition and control.

i 350*F The restrictions on starti r coolant pump with one or more RCS cold legs less than or equal to are provided to prevent RCS pressure transients, caused by energy additions from the Secondary Coolant Systas, which could exceed the limits of Appendix G to 10 CFR Part 50. The RCS will be protacted against overpressure transients and will not axceed the limits of Appendix G by restricting starting of the RCPs to when the secondary water temperature of each staan generator is less than 50*F anove eacn of tne RCS cold i

leg temperatures.

e i

i

.i Iq(

BYRON - UNIT 1 8.3/4 4-1 lt

(.

e h

.'L t

---a

_,__,__,,,a

,-m---

-,,,w._wwea,--om,,mm ee-4,

-w4, w+.,

ye,,._p-y

.-w-

f

,i

- i~

1 f

REACTOR C00 SYSTEM BASIS i

PRE 53URE/TEMPGAT1]RE f.IMIT5 (Cantinued)

Although the pressurizer operates in tamperature ranges aeove those for dich there is reason for concern of nonductile failure, operating limits are provided to assure essentibility of operation with the fatigue analysis perfereed in accordenes with the ASME Caes requirements.

a No R%sve.hw valves; The OPGASI1ITY of the PORVsjer an RCS vent opening of at least 2 square inches ensures that the RCS will be protected from pressure transients dich could exceed the limits of Appendix G to 10 CF1t Part. A0 den one or more of the ACS cold legs are less then or equal to 3802Fufither PORV has adequata i

relieving capenility ta protect the RC3 free 'overgressurization wnen ttre transient is limited to either- (1) the stara, of an idle RCP with the secon-

= less than or 1 ta 50*F dery wtar tamperature of the staan genereta esve the AC3 cold leg temperatures, or (2) the start of a uma and ita injection into a water solid RC3.

op h,

'7

3/4.4.1D STRUCTURAL. Inie M if The inservice inspection and tasting programs for ASME Cade Class 1, 2, t

and 3 camponents ensure that the structurnt integrity and operational readiness j

of these cassenents vill be esintained at an accaptaale level 1.nreugnout tne These programs are in accordance with Section XI of the life of the plant.

ASM So11er and Presaure vessel Code and anglicaale Addenda as, required by 10 CFR 50.55a(g) except were specific written relief nas caen granted by the Commission pursuant to 10 CF1t 50.55a(g)(6)(i).

Casuponents of the Reestar Caetant System were. designed to provide accass-I ta permit insanica inspections in ac=ordance with Section XI of the ACME Seiler

)

and Pressure vessei Code, 1s74 sdition and Addenda through s - r is7s.

t

=

IS l

ht ao Mo.)

m PcM o.&h A o-

.. a m

l u-+ "

,_, _ y p m 4 n-e. Y l

M v % a 1+b d r& &

@ & 90R.V M M M M i h j

M M,O f dP t

M M M ALa. M to Q e h y p (EFFy)

, ~,.

j QpF-i 6 fwies., m u A NDT O.

are intelocked WE Ch RMR Rcs surm uolatm valves 8901 A and 370 t A l

p.,

A" +roin t&de. raw 3.e. pressure. irnwstwtfer and valvr3 89016 cw S

Mae NSE Prewe. %W hwin0 v

8 3/4 4-15 SYROM - UMIT 1

(

are. inke lo<.hed we ci "B" M n d O"5NW" 8 70 4 6 ed M02. A, pre vt.hiJ boa r2.HR. sue.h r ellef valves M "#^[

Powe r from valvn irlativerkwt4j iJol4 W3 9i

_......f H.tk 140 ladim cda bl%+v hc. 64 r2.gn_f/s enAf.

~

i

' ~ - -

^~

l l

1

- m u.

a_.__,_,.

e 6

ATTACitEDrf C (Boron Dilutior. Protection Esckage)

1) Table 3.3-1 Reactor Trip System Instrumentation (pg. 3/4 3-2).

Item 6.b. delete the words "(Trip Brk Closed)" and the Applicable Modes shall be "3, 4, 5" not "3*,

4*,

5*".

Change the Action statement from 10 to 5.

Delete item 6.c. in its entirety.

This changse is necessary for the addition of the Boron Dilution Protection l

System (BDPS).

2) Table 3.3-1 Action Statements (pg. 3/4 3-6).

Delete Action 5 and insert the following:

4 i

" Action 5 -

With the number of OPERABLE channels one less than the f

Minimum Channels Operable requirement, I

Suspend all operations involving a reduction in boton a.

concentration of the Reactor Coolant System and 1,

b.

Restore the inoperable channel to OPERABLE status within 48 4

hours of open the Reactot ttip breakers, and either j

1)

Verify compliance with the SHUTDOWN margin j

coquirements of Specification 3.1.1.1 or 3.1.1.2 as i

applicable within 1 hout and at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter, o_t_

a 1

1-2)

Close and secute in position by mechanical stops or by removal of air oc electtical power, valves ICV-8439, 1CVllB, ICV 8428, ICV-8441 and ICV-8435 within 4 houts and verify that they are secuted in the closed 3

position at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter."

j 6

i This change is necessary for the addition of the BDPS.

i l

3) Table 4.3-1 (pg. 3/4 3-9) Reactor Trip System Instrumentation Stttveillance i

Requirements.

Change #6. to i

"6.a. Source Range, Neutron Flux S R(4,5) S/U(1) N.A. N.A. 2##, 3, 4, S I

b. Source Range, Neutron Flux' N.A. R(12) M(9) N. A. N. A. 3, 4, 5".

Item 6.b. was separated from 6.a. because of its reference to the BDPS which is only applicable in modes 3, 4, 5.

4)

(pg. 3/4 9-1) Boron concentration.

4.9.1.3 change "lCV8430" to "lCVillB, ICV 8428".

9

=.

. m.m. ~.

z.

.m~=

. =. _.

.=

_u _. _

v t

PE0f 3.!!PriE# COPY r

y9

, (3 t

G h1 4

- 3.

r,

~~ ~

~

41 i

<) f J.

j

. I,.

~

.<i c.

~

i

.a.

=

-a

~,,.

s J

1 4

==

s a l.

= e.\\.

et 4

y

{,3

~~

aa a

]

sg-

[

g Ewk

.c

=

webb

==~~='-~~

c.

~~9 m,~~

~~I 3Y1tCN - UNIT 1.~~

~~3/4 3-Z N.~~

I,
- Ja If 1: U
...,..a... i m_
-.r,--.,.;,--.w.
.,,e jj l'
~ ~ ~
.TE.
~ - '
~
.=
.2
~
~
b TA815 7.3-?. (Continued}
AC"TCII STAT 9EffT (Continued)
~
ACTItDI 4 - wita the nummer of CPGA8LE caannels one less inan the Mnimas Channels CPGA8tJi requirement. suscand, all coerations involving i
j positive reactivity
- n:.
..O ACTIOlt -
numer of CPGASI.E cnannels one 1
". L,,;m-J' requ1_, __ n.... 7~diiiEIIance wita' tne "A A "
Channels.
e Is of Soectfication-3.LL1 or 3.1.L2, SHUTtXM8.
1 an e, witnin L hoburg enes per 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months p.
g r.
ACTItDI 5 -With tDe maner of CPGA8LE cananels one less taan :ne Total a
>.O W of Channels, STAT!!!P and/or PWG CPGATICN say procaed provided. tne fallaeing consttiens are sattsfied:.
The inoperatie channel is-placed in the tripted condition a.
within L bour; and.
n.
k.
The Minism Channels CPGAELii requirement is set; however,
~~ne inoperable enannel say be bypassad for un to 2. hours for surve111anca taedng of otner enannels per 5pastficatise emLL.L..~~
y ACTIUlt 7 -Witfr tas-nummer of.CPGA8L1 cnannels one: less taan :ne Total L
1
~~amer of channels, STARTUP and/or PWE CPGATICN say ;ncaed unti1 M.-~~
- of the next required ANALCG C:iANit8L CPGATICNAL 1
TIIT providad tam inocernste enannel is placed in :ne tripsed candition witzin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .
t.
I-l!
ACTION S - wita less ther tne Minism Nummer-of Channels CPGASLE, witMn i
I hour dotarsine my asservation of the associated permissive-annunsfator windom6) tant the interloca is in its reautred state for tae-esiseng plant enadition, or amply soecificadon 3.0.3.
q witn tDe nummer of CPGA8LE. cannnels one less taan tne Mnimum 1
ACTI!31 9' Channels CP9ASLE requirement, to in at least HOT STNtDirt witnin 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ; henever, one enannel any be typassed for un ts V'
1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for surveillance *eting =er Saectficatton 4.3.L1, prwided.tne otner enanne.' is CP GASLE.
ACTIQII 10 - wita :De wof Es1tA8LE cnannels one less taan :na Minimum Channels QPGASLE requirement., restore one inoseraale enannel to OPRASLE st :,as witnin 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or ocen :De Reac.ar tric G
breakers vitnin :na next hour.
ACTI!3011-wita :ne nummer-of CPGASLZ cnannels less taan ste Total % scar of Channels, aceradon say c=ndnue pnvican :na inocertale enannels are placed in tne tripsea c=ncitten witnin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .,
1, W.
STIQlt - UNIT' 1 3/43-4 9
~~'***m.~~
ev.
r-
,,__,,._,__r,_,.__._.,,
-...m,
.,.____,_m.,,,_,,,_._._,,,mm
_,_,,,,,,-.,_.w.,_,__.,m.,m
.c
- N sa..e
'W.e ww=*
-e
.=%a r eto la d
,. e raw.+
" A A "
m h h +Aa f OPEPRBLE C$ &
O) dh, hM hCTloN 5 me &w O A euge w j
~~a. 4 p l cat o g n e~~~
W m a h c M A e.f
+L.a W Ca>4o~k-S& mi b. R&aAma-- A & W M lo O PsyLAG t.E
&M mW 'l 8 W p h h h MM ov NA:
0 V a~fyg W a~x. wJ-( +La-
)if0TDoww W W of d m 3, t. I. I o v 3, I.I. 2
~~A oriW 1 on-d cJ-W On.<A P 'I h av.~1 W~~
~~m av~~
~~2) h w a.<ma 4(xsh%g w e<s o-%n av % w%~~
m w n n a n,v I tv ll13,I tyf4493 i CV - 8 43c1, d CV - 8 4'W l
. ~. -
m4 d.C v-8 't 3 5 & 't h etw2 aml MAw% h h(
t g<.%.Fim LF M 6
Ch
~~12. NW b 3~~
a A
N l i'
~
a -E.-
.w PRDDF & REMBY C
\\i
(
..g
.~
e
~
)
e*
N N
N N
N g
g M
N gg g
EMI:
4 2 a 2
2 ;.:
j,
):
1 50.
4 4
4 4 4
4 494 4. < <.
~~"y g~~
i i
s s i
i s<sssi=,
u_
s 1,
Ili E3 4
4 4 4
4 44 4 4 4 4 4 w,
E
~C
=
s ss s
i its i
~~s. s si a~~
222-.
e B 24333 8
S s
W s
A An 5
g 27.,
a-R Re*
~~5 *32 8~~
"'8 2
t Ratt l
I a
5 4
\\
224.,
.n 4
3' m
M
~~'u.~~
~~1 1~~
AI 2
g
.e.
P 3,
3.3a== -O 0%:-
. =
2
=
=
=
=
~~= = = =~~
\\
~
7 s,
s.
=
3,
'4 4
4
={w l
w w *
~~w 3,g s w~~
w n s
=
m.
l 3
?
3 I.
4*
I 1
5 1
-8
~~1. s~~
.. E
~
9 u
~
~
27 k
k 3 )
=
8
&g g
g 2.*u t
3
~
k i *t i t.
?
,1 14 Ai 2 A 2.
E a_
kt g?s E x: a - t. ( =
ci:
~
u 2
. s-1.
.s.
-2
g:
5.:
E a.f:S a,*
t : :
i'*L 5
~~4. 'c ut g~~
~
y3 s
s L.g a.
eds !.7v ga.
E..C 3 -2 i
v s.
5 a.5_ 2:
14
~~x v:ve i~~
I
. I_
~= -
y m
2 a 4
i g..
g
.-~
~~m. - u,,u.1 uu-.~~
i h
u-9 ly 3
.3.
_,,,g
, f
.. w. 3
^
2 ::...
=
.
c l
..Z A
t c
uu arm.= e==.
4
[
3/A.1.l_90mHf CaleCEmtATTCII I
f i
.. esa,. % to M3R CMitATTOII w
o g(M V
o*-
p 4
3.2.1 The amres emmenstructeur of al ens of tao anester Caetant
/
Sysemer amt tan reteniing canal saml1 to stafnot ustfore and, surfTdest is ensure tant tse more reserfetive of tae felleming reestivity essettfesa is 1
O,
)
L a;
AK of 0.5 or less, or g
l' 1s.
A terem a=======stfest of grestar tase er equal ts 2006 pse.
APWLICMILITf-MEk
?
mae 1
wfte tan regsframents of tan ansve spesificaties not satisffed, fummeistaly L
summed alt apursstems involving CREE AL7WATTIBIE or posittve reestivity J
causens and initissa and continue terusten 44 grestar taan er equal to 30 gem of a soluties cassaining grossar taan er equal' ts 7008 aus meren or its equiv-j
%.y}
alemegustil Kg is. ruessed ta less taas or agust ta G.35 or tas borne j
~~==== e=4 stem is restared to grosser tant er equal ta 2000 pas, dichever is~~
{A sure reserfettve.
1 (Sidsmea )
1-j ura m,m* W --- K.335 Q,.
a t
P 4.f.1.2. The more restrictive of tan ansve the reestivity coneftfans small be detamined prior ta Emmering er usasiting tae reester vessel head, and s.
L-1 A
Vttlemmi of any 1;- ^
.e esseret red in essasa of 3 feet fres tts, fully insertad posittom vitain tan reestse vessel.
j
]
4.1.2.2 The bereur crassmerstfen of tae Reestar Caelant Systaur ane tae refueling canal small ne estaretnedyw wcat analysis at ieast_
per 72,.usurs.
1cVtil8 lev 39 Q -W^ S H 4,I w e e s w I w e+34 he verffied closed C
and secured in t n,
'

"^- C T',
2 5-M staes or :y consval of air or eiestrfcal
'Istves A S.I.J s ti pesar at least onen per 31, says.
A "rne reester snail ao saintaines in '<!ct 6 nenever fuel is in tae reestar vessel wtta tae vessel need clasure noIts. Iens taan fully tansioned or vf ter tan meet. _. "
ST1EBt - UNIT' 1, 3/4 9-L
%Y I-u
=-
_ = - - -.
ATTACHMDIT D Circled items noted in this attachment have been previously submitted.
1)
Pg. 3/4 9-10 Containment Purge Isolation System.
4.9.9 Delete " Manual Initiation and on".
There is no specific manual initiation for a Containment Purge Isolation.
It occurs on a Manual Phase A or a Manual Phase B.
This is covered in i
3/4.3.2 Engineered Safety features Actuation System Instrumentation.
l l
e I
~
t i
1 i
1
... -... ~ ~
'tt8f8f N CMMAT* CMS [
h kh $,
TfS'"E 3/4.9.9 COf71
~
~
L m Anu au da a*02 CMRAUCM-4 Ata.se = sawn.4
~~3. 3. S The Cantai~~
'!... :...d snel'! to CP GASL2.
k Apot ID8II I"*:
Caring C".HE AAM. se anvenant. of tr-attatas fuel witnin tan curta1 mess.,
O
~~n. w = se v e n. 4 l~~
a ' Witat tam Castai
. J '.;" h noperseIe, !ase ease of
. D' tam purge volves providttmy 4 Trees assans ftse tae cantairmans.
semaga==o ta tae out.f.de atmosenere.
t 3.
The previsions of Soesificacions 3.0.3 and 3.0.* are not solicania,
~
I t.
c.
r f
$0HVtn.! McC1 TEM.6-i,Ti l
?
M6g* 2,$4UQI*1W i
Lcs 4.3.5 The Castaf an" saati 5e daeanstruend CMilASLI witain lott hours prior in ne surt of and as least once :er 7 f.ays curing 3
C:NE ALT 1!IATICIE sy veriff ng cat contairamas ; urge isolaftf an oc=urs :n i
l i
a 153r tast signal f?se eenn of tr+ *#rment.
~
0~-_T h
restation sanitseing instrumentations csannels.
l t.
Q>
D
~
sp Y
t i
i
~~c. R rrnum - unc :~~
~~2/4 9-!.2~~
~~v,\\~~
_(
_ r-.
..,s.y..m
.e.
-.-e-
--,-.-,-,-,..,e.,.,,,,.,,.,,,,,,,,_.,,__---.,_w.
,_,__,,,..m,_--,_,-,.n_
_.....~.a..._;-_.
i ATTAQWEDrf E
{
Circled items noted in this attachment have been previously submitted.
I
~~1) Table 2.2-1 (pg. 2-6), Table 3.3-3 (pg. 3/4 3-17), Table 3.3-4 (pg. 3/4 3-25, 3-26, 3-27), Table 4.3-2 (pg. 3/4 3-35).~~
The alnve referenced tables have been rev bed as noted on the attached sheets.
1
~~2) Table 3.3-3 (pg. 3/4 3-16), Table 3.3-4 (pg. 3/4 3-24), Table 4.3-2 (pg.~~
3/4 3-35).
Item 5.c. has been added to each of these tables as shown on the attached sheets. This change is necessary because a safety Injection signal will l
cause a turbine trip and feedwatet isolation.
1
)
i.
1
.4 i
l i
a.
l 4
i n
i 2 =
=
_. m =. _.-=-=-----------._-;..-
.---.m--_._..
... _.. _ _ =.. _. _. _..
.i
,v
(-
g j
( f a
IAsag 2.2-3 (c.atiew d) i
'tM SEAclan isle sysitM instaunfulA!!aN inir sticosmis 2
s scuses l
9 Esans 4
101A4 fuuClianas unil At4ouamCg (IA)
I m
Lair sgges Ni miaunatt veuf I
r
~~12. se.cter Coelaat fl w-t w 2.6 4.n e.6~~
> sus et i e
>as.2% of loop ystou-ty>
~~2nsion tiew" l~~
~~n.is i~~
~~13. stamm Generator Water 27.4 rit:13' l.h~~
>40.a1 mi parrow 136%ofprrou I
l taval Low-tow Ipp range lastrument enor.dastruecut s 4a i
q;;. -SaLS uwg l
14 untervalt4pe - Reacter 3.3 4
4
~~2" v s-H n_H-valth ifkh %~~
N l @S ars -
h S L. 5 CoolantPumps 1.o
\\
l'h b e
hf l
Is. un.acrirespiency - pe4ctor 14.4 coolant rumps A
o J.
i 16.
IurIM ir 640 i
ab'il Y**dh SYO M**'le6is l
(
.e it_fransure N.A.
N.A.
el. A.
ps g 4.
b.
Ius-hine 6 top Valve N.A.
N.A.
N.A.
11% apea 11% upen Closure A.44
.i i
17.
safety Injection input N.A.
N.A.
N.A.
N.A.
N.A.
c3
(
l from ISF J
saa l
j I
la. Seatior Coolang Pump N.A.
pl. A.
N.A.
N.A.
N.A.
f2 J
Sic 4ber Posillog Irlp Q
[
g.3 ato,sla is.i si w Nm b
2 i
1 1
l D
i-j 4
r0 1
, - - =...
L.
fi l'
TABLE 3.3-3 (Continued) e
~~e g~~
~~ENGINEERED SAFETY FEATURES ACTUATISH SYSTEM INSTRUNENTATION~~
~~I z~~
e E
MININUM q
TOTAL NO..
CHANNELS Ci;ANNELS APPLICABLE I
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MDDES ACTION g
6.
Auxiliary feedwater
!t a.
Manual Initiation 2
1 2
1,2,3 22 lI t b.
Automatic Actuation Logic 2
1 2
1, 2, 3 21
~~l and Actuation Relays~~
!'!l c.
Sta. Gen. Water Level-Low-Low
~~1) Start Motor-~~
!,l 1:'
Driven P 4/sta. gen.
2/sta, gen.
3/sta. gen.
1, 2, 3 IS*
?
, -1 in any opera-in each j
y
/
ting sta gen. operating I;
y sta. gen.
i
ll
~~2) Start Diesel-~~
)j' Driven Pump 4/sta. gen.
2/sta. gen.
3/sta. gen.
1, 2, 3 IS*
l in any in each l
operating operating
{
sim. gen.
sta. gen.
m C'3 j
d.
Undervoltage - RCP 4-1/ bus 2 of 4 3
1, 2 19" Q
[
~~l Bus-Start Motor-i l'"~~
Driven Pump and c
l Diesel-Driven Pump e
h i-1 i
g<
~
e.
Safety Injection -
Start Motor-Driven Pump See item 1. above for all Safety Injection initiating functions and
{
J and Diesel-Driven Pump requirements.
nC3 e
f.
Division liESF Bus
]
! _CD Undervoltage-
)3 Start Motor-Driven Pump (Start as part 2
g 2
1, 2, 3 18 i
l of DG sequencing) l l
.a R00F & RM CDM g
a a
E i
~
~
g 3
i E
5 e
e i
9 e.
4 5-n u
N M
g M
M M
h d
J> o 3
g
-3 1
i.
1 w
d G
'E s
s m
u 3
a
=,
3 me
.8 a
J s' wg 3
a n
~
u g
's n
""~
S; 3
j k
E 4
w s.
g d
S h
,e e
=
~~3.2 i~~
3 v
h C'
W
.5 2
3 w.
I
.2
?.
T A
g g i. 3
& I I-g dud a
. 9 l
ai i
.L, 1
2.
.o o
y
==
=
==
y ti 1} maa:
r. 42
'=3 ae 4 -
f 2
1 v
5 a,. =.
b.
. w.
~~a. - >~~
3 u
u
.,-a.
.u B
=
as
.a
g aS 3*
41 L
aV m~T
, 2.2252. _n.e o
-e e--
w s.
.o a
4 =.
w muw a
y I.;
l 4
g s
Jus e
a e
a s
bJ 4
4
..d synon - UNIT L 3/4 3-13 l
3,9 l
y-

~~wyy--.-.,,~~

,g
--r
_y
-,.y,y, g-my----,m,n.-
,---,yg---
.,w,
-,--w w
w
+
.e
---e
.i I
4 1
TABLE 3.3-4 (Continued) i E
I E
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS l
i z
TOTAL SENSOR TRIP ALLOWABLE
.E FUNCTIONAL UNIT ALLOWANCE (TA)
ERROR (S)
SETPOINT VALUE Z
-4 e
6.
Auxiliary feedwater l
j a.
Manual Initiation N.A.
M.A.
N.A.
N.A.
N.A, b.
Automatic Actuation Logic and Actuation Re1ays H.A.
N.A.
N.A.
N.A.
N.A.
c.
Steam Generator Water Level-Low-Low-Start Motor-27 1 18.28 40 0 37 /
Driven Pump and 3Get 1.5 of of w
D Diesel-Driven Pump narrow range row range i
instruement instrument w
3 A
span span w
S3L8
- / 2..
e-v
.u
,x g r ea d.
Undervoltage-RCP Bus-N.A.
N.A.
N.A.
1 C ECF j 4ws veli-se lM8 i GT. RCF t i
Start Motor Driven Pump and Diesel-Driven Pump Lu. vuii v.
i GO^,0 seite)) (i571 va?ts) j e.
Safety Injection-m Start Motor-
~~t3 ij j Driven Pump and See Item 1. above for all Safety Injection Trip setpoints and j~~
Diesel-Driven Pump Allawable Values.
r
'3 po i
~~acs i~~
N E
m sn sa 4
^j
_o liy l
{:
t
~~i f~~
~
TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUNENTATION 1 RIP SETPOINTS
,.I g
TOTAL SENSOR TRIP ALLOWABLE i
E FUNCTIONAL UNIT ALLOWANCE (TA)
Z_
ERROR (S)
SETPolNT VALUE
{;
i.
q 6.
Auxiliary feedwater (Continued) f.
Division 11ESF Bus Undervoltage-2870 volf5 2730vo4s Start Motor-g Driven Pump N.A.
N.A.
N.A.
.JL#!"
W 1 '
j l g.
Auxiliary Feedwater
!l Pump Suction Pressure-Low (Transfer to l
Essential Service Water)
N.A.
N.A.
N.A.
N.A.
N.A.
m>
r Y
7.
Automatic Opening of N
Containment Sump Suction i
{
Isolation Valves i
a.
Automatic Actuation N.A.
N.A.
N.A.
N.A.
N.A.
m
~~43 l~~
Logic and Actuation Relays c@
b.
RWST Level-Low-Low N.A.
N.A.
N.A.
N.A.
N.A.
go i
Coincident with i
Safety Injection See Item 1. aboye for Safety Injection Trip Setpoints and Allowable Values.
l E
e C3 N
==<
O 2'
!I I
t TABLE 3.3-4 (Continued)
I E
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUNENTATION TRIP SETPOINTS z
TOTAL SENSOR TRIP ALLOWA8LE O
~
FRROR (S)
SETPOINT VALUE E
FUNCTIONAL UNIT ALLOWANCE (TA)
Z 8.
Loss of Power
~~2. 27ao volts r~~
gBusUndervoltage N.A.
N.A.
N.A.
28.a polts 20 'O..;.. as g g,g 4 a.
l.16 timt dt
'a
^a I..;...
4 b.
Grid Degraded
.2 374% Volis d
yoitage N.A.
N.A.
H.A.
3804 volts N
& t!z^ 22';y e
~~9 ?! i!:2 C;i~~
$ '.:2 7. k p.y..fg 3:06
@Ib 4
9.
Engineered Safety d
feature Actuation System Interlocks N
a.
Pressurizer Pressure, 1930 P-ll N.A.
N.A.
N.A.
1 W X psig i 2050 psig w
O i
b.
Reactor Trip. P-4 N.A.
N.A.
N.A.
N.A.
N.A.
c.
Low-Low Tavg, P-12 N.A.
N.A.
N.A.
550*F
> 548*F and l
7 SS2*F
$.~_ D d.
Steam Generator Water See item 5.b. above for all Steam Generator Water Level Trip Level, P-14 Setpoints and Allowable Values.
1 (lligh-liigh) c.3 l
~~1 5Pa 4~~
~~sa Gi!~~
c2 1
C:3
?
_o e?
i 1
j J
-- n ;. _ _ n - 7. _ _ _ g _ _ _1 1
~
e
~
~
~
)
i O
a=
aa aa j
~~5ith a~~
a aa aa
.: a I!=
a a
aa aum; e
e
-e ee J
i S
r*I, Enz I, k ee 4-
..t i
s i.
a,
=,1 a a, i
1 1a u
3 j
{
r g
5
~
l-8 PRUDF& REYU CDM
.n.i
=
- e 4_
=
]e-::sm zuzf=
}.
4
=
e am a 9
Q q
e
~~i a~~
'm,.
Y v u, g.a
==
l m'n h $\\
5 $
Y 5-E*
.. In.e g
g 3
=
i 1
i a
A 5
N
$ n d e m
4' 5
=
=
a 4
a 9
y
. ;3e e
eea ee P'
5 F
l 1
P-M rs I
s e
- o 1
3 r:
2 r a s
-: 3 16 fp 33 1:0 t
r 2
.. '{
4,
~~l' O _f-1 5.. 44~~
? '.1
? [
6 f
E *
'I si "S bl
!b I
I y 3 e :-
2]
geen p2. :
E s
7.
g u.
, t,_3
(
r a, -
,,1
.I,d.:
g'ig w
<=
-:q
- w.
<u-l 3g a di 4
i 4
i i
O.
ta a
a 3YRON - WtTT L 2/4 3-!$
II1 i
~ *
~~e 9~~
\\
,-----,w
--e,-n-.
---~-.,eme.
r-
---,,,,w-,-ww,,--.----.-e--.~-w--.~--
.-w-,.,-g e, mwm vwywn,,-,-
, w v-
~.
~~
-=e.-
. m PRDOF & LEE # Cyr d,
es E
Mk=
2.4 e
=
1:
g s
5I
=
eee e
e e
m i
h I
5t u
a.
d d i.4 I
Ja A
8' 8'. :
.d4
=
y.
g d
j x.ss i 3
l3 a
E n.
]
c.
li.I 1
1:
Es 11i str
,,J
[
s-s-
5 t:, s i:,
.n.sii
=
~
gm m--
.sl 5
e-j i
i i
i-t 4.
g 4
!s; g
M.
~
s s
s
~
d-e t
s~~
5 s
.=
=
.=
i
.13 is
.!3 o
i f.33 3 ?
n
.I.f _
s 2'
j s
a
44
_=
3 :.1
~~= a :f 3~~
~~1 3:a_s a.:~~
S li 8
ser o
gor.,a @g<
-v-: s 1
t
-3
~~g2' 2v i :~~
~~s2 8~~
z-
..: s y-3 }= : 1.H.s. q 2 :a4 s, 1.,2
-s i
aan c
as-D 3
r g(4 3_ 3 4
4 i
4 54 i
q) t 1.
3/4 3<.15 smul - un1T t
.\\ L
's
.i
.7..*. + y :~h,,ge. x.,.:s, y.;.
.,,y, 1-
- - - _.,. - - - -. - _ _ -. - ' ~ ~ -. _. - _.. - -. -.
~ ~
~ ^ -
1 q
E~/ & REnE# CSFf i
(,.17' s
~
r ~~
i
< s.
L
., 2 8
,1 :.
a.
. a..i. :l,_n..:
. 4_.
=,
1
+a-n s
_,D-5 3
wt 44 I
E~
3
.r.
?l l
~~' I a~~
n* S $
sf I
e1-
=
a n
T-4 i
,t 4
4 ff S
N 5
wt AL vtk E
wt 1
c I
Ig'-
D B
4 4
e e 4
e a
e e
a a s
a 1, 3 a.
f._._.
.\\
eD+9 1
n \\ R.
n
~
4 a
~
E
.. g 3
E2 Q/+
4%)
i.
i
.ed d
ll.
[i d
Q
^'
4; p=
u:
1
=
as y-g l,i.(a!O=.?
1 0
. nr
_vs s
~~e e :..:.:~~
xx
=
3 : 4 3.
t nt 3..:1 24
)
I i t d j' )
e
~~. :3 as c 7 7 2~~
o 1
E g e n.
~~i..:-~~
4 g s.e su t
r-
!. I s_3n l a d.
o 1
-s h
-E.
as: 2:
1 ;.2 s y y:
e a
k
!. 4 2
an 9,1,td>5 l'
0
, n
.-.--.---m,-
,,,,--.,-m,- _, _,..,,. _, _,..,
,w-
-_--._m,,,
%~-
-,,,,,,,,,,y-.,,,y,%-,,,-w,,.,,
,---.w-.,m-
.n
. ax
, m m;+;
.p
. o 33g.;;
~~W 3..-~~
Jy' @
s'g, y'). 7
- - - - ~.
.._m.
.' ::sh qt J[
~~3. 11 5 PR00F & RGB d~~
.n
=
. ;94
s
~~
~
~
~
~
~
~
f.
5-J.:
n' s' &
9 r
<g 5
1 9
N fr:
wa-ae a
a
=
e
=
3 e
=
=
a
.w>
2 2 31 4
4 4
4 4
4:
4 4
M'a m
=M
=
=
n y
n sy 4
s
!_3
=
E 5
42 4
4 4
4' 4:
4 4
4 sK e
i s
E s
yK s
s w
.322g
=-
=
~~423-~~
=s i
i s
e s
.s s
z 25 t
3 a_
32.
.4
.a
=
4 wk ii,z s
s s.x ss x
e t
=
i E
=,
i
/
4,3 w
y ss a
=
=
s a
as a
w II e
H a
1 44 4
,y 4 4 4
=
s
~~O ii w~~
s is w
w w
,)
l
.P 7
w i
3 h
i,l
.l i E W3 4
II 4 a
i
. E 5'4 f5 t
C 1 :: 3
)
a t 5
~~i u~~
~~li t~~
~~!I t~~
u
~~: s~~
~~2. 3 3 "t 13~~
'I t t 13 4 M*
??
2 2 M4 t i t
~~Vg.~~
l
~~3 1~~
y
'g it 31 *5-2 31
3
~~- 3 31 la E~~
.>1*
?
~~= "$ 2 !.~~
,l s r 2 - *I S,P 3 4 e r 2 E
4:
2 13 11 3
1 1
g
.s,q 4.r :
1s
-3 j
4.r w
~~z4 w~~
~~=wm~~
~~i 34i J~~
i i
31 4 4 di i i J
4
[j
_4
!Y14M - UNIT I, 1/4 M S Ib~
a e+-,.--
,y
__

ML20090J314

Contents

Text

Subject:

Dear Mr. Denton:

.==

= = = =

.

Navigation menu

ML20090J314

Text

Subject:

Dear Mr. Denton:

.==

= = = =

.

Navigation menu

Search