ML20081H138

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Proposed Tech Specs for Licenses DPR-44 & DPR-56 Re Requirements of SRMs While in Refueling Condition
ML20081H138
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 03/16/1995
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20081H128 List:
References
NUDOCS 9503240106
Download: ML20081H138 (9)
v • d • e


Text

_. _.

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I 1

1 ATTACHMENT 2 1

PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 t

l Docket Nos. 50-277 50-278 License Nos. DPR-44 i

DPR-56 TECHNICAL SPECIFICATION CHANGES List of Attached Pages I

Units 2 and 3 l

103 227 228 (and inserts) l 231 (and inserts) 232 1

{

1 i

9503240106 950316 i

PDR ADOCK 05000277 l

P PDR

. 4

(gb 2.J 3

[

'PBAPS f

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3.8 control Rods (Cont'd.)

4.3.8 Control Rods (Cont'd.)

4.

Control rods shall not be with-1 4.

Prior to control rod drawn for startup lor refueling J withdrawal for startup.

unless at least two source

'ine aurina refue' inal range channels have an observed verify t1at at Least count rate equal to or greater

-two source range than three counts per second.*

channels have an observed count rate of at least three counts per second.*

' 5.

During operation with limiting

5. _When a limiting control control rod patterns, as deter-

. rod pattern exists, an mined by the designated quali-instrument functional test fled personnel, either:

of the RBM shall be performed prior to with-

~

' drawal of the designated

a. Both RBM channels shall be-rod (s).

operable, or.

b. Control rod withdrawal shall May be reduced provided be blocked, or at least three source c.-The operating power level range channels for shall be limited so that -

startup.or at least two the MCPR will remain above-source range channels for f.

the fuel cladding integrity

. refueling' have an m

safety limit assuming a

/

observed count rate and a

"~

single error that results

.. isignal-to-noise ratio on in complete withdrawal of

~ ^ 'or above the curve shown j,

a single operable control

' on Figure 3.3.1.

i rod.

/

l C.

Scram': Insertion Times i

C.

Scram Insertion Times i

1.

The average scram insertion time, 1.

After each refueling outage based on the dcenergization of

'or after a reactor shutdown i

the scram pilot valve solenoids that is greater than 120 as time zero, of all operable days, each control rod shall

.~

control rods in the reactor be scram time tested with power operation condition.eE',J3548,the' reactor. steam dome

, $ptMffj. preisiure 'gr~eatei..than or.Y.

i M ishall be no

w.... c.--mc.r, q.g.9,

. greater;than: grid g.g.g, g.p.$.7 2 7

l 't "800 'psig' prior to " ~

,.5 Inserted from (Avg.? Scram.Inser$.;tionTimes'fs Fully Withdrawn

  • r. #; F 0.375 b u y# 5 g; Power.'9$ cram t r

.i.:n-a.mjW is'not; required'for. control f

. _,. ~.

5-jn'.t rods". inserted per

~

. 20 50.90 W s E Specification 3.3.B.1.

- 50

. y ~ *2.0 9' ;M v'

90 3.5

- ~*,~

~

-l'03-Amandmant No.14, (I, 79,142, I#%,

~

200 SEP ! B 594

..C.

s

i 4

Unrh 2anJ 5

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PsAPs

~

LIMITINd CONDITIONS FOR OPERATICM SURVIILLANCE RZOUTREMENTS

^

>..
: ? U P :'+:Y -

3.10. A.N.... ; :,; s... -,

e, b '(Cont'd) 4.10.A directional centrol valves for j.c.. j.q remaining cont =ol rods shall

.,j,.y:. y.3.a ;;'

be disarmed. electrically and

' ' W / [$].y.i

.E ' ~ Jsufficient. margin to.-

7 H 9MN.z,. "'1 ^. * -

.' criticality sha11'be J

"f

~

, '.. s

/..

demonstrated.

~

~

M f a pejiformed oUtwo'controlfred, y,(.j; g c W'hilijih'..the iefuel mode, except.,

.c.~If maintenance is to be

  • !? h-Q ssts'peii,1fied in' 3.10.B.2,- 3.10.*B'.4.-

,.drivesf they'.must be separated. W Ci" Iaiid 13fl0.'B!5, iwo SRMs shall be ' '

f,*

lby nere than,two Control Cells. ' -

,".7 operable ;

j

~

in~any.directicn.,

',. i' E

1.1.m:.-.;. t :..: s 6 f D "t3 tie [.one 'SRM[ channel is required

d. W Yp. h o!!Sp M.....tM. umber"of SRM8s 7..@

52.' /,0nly oierabie duiiM ' spi'sl YW r

lareT available als 'defin'ed in.

(% VW:6ff h d-or feload Uhen the T

C specification 3.10.B.

fueled region includes only that SRM detector.

I6.'Any numbei of control rods.may be

- ;O t

~

I withdrawn o'r. removed from the.

A' '.(~q.:!fN"'e.h * ' ' 9 ~

^

.~ ' ~ reactor corefprovided.the

. g q..

' 1,

P

~

7 i ' h ?.

('i4-: fallow'infconditionsare '

..e

1. ' Prior'to. entering the; refuel satisfied:... t :.

~

' Qf 'ff,,'f. '1

" ~ '.

. [;

ic..jm6 del'nd,every12: hours.thereafter

/

a c

a.,The3eactor m' ode switch is '

>;'y v f..W.gg'1Wii thErefuel5de,1. '.

' I.

. locked:in'.the ? refuel"

. i"

.j:.: dhii6nMheiik, sh'all'-bef erformed y

' p 7 f,,,

,jos! tion'.iThe.~ refueling

j. R/fM fa'cli~ required 'SRM[.

y interlock which prevents more t..

1

~

' ' jifthanjne ' control rod from

.j M':g.0..:W'.jjn..'" 4 ' ;,. p':

- e I ;?

('p:N:

' %eing withdrawn may b'e

u-

~

js

?

.f,..

' )3ir

.-$p;,y g,.,,

..g :

W

~ bypassed on a withdrawn.

. :g control r6d'after the fuel,,,;.,'

s

~

..;.~.

72 y

n.:

b' lies in.. the cell

1..L,..W 5,.,.I.?I M. w- +. : E l....'~ .S
g.. -

~

..G... :.. a. s_s. e..m.in. in...; (ccx2trolley) xsa...../

.c

. v.v conta.

,::n. :*.=-

g:

g.g.

.f...A that control;. rod have been...,.

%y,Q[..t q..,yl4 i.% p ?.E r Ap,) F V, :

1, 7,,

e-:.N.M%emdrsd strom,the, reactor i. core,. p, >

4, n.M, :.u.. ;,.

.i 2Agg'b "9gQOB.q core Monitorine tg:gvg> ~g y' W: y.y g

.. ' I MCore iMonitorincr re:afe..

~ 'ified.. in t3.',10...B,n.7.,,,%-.;$-v. >., nw a:m n

0-

,.+..

a r_

-.wm _

.,,,.,,j 2;.E 1 1.., }P.r..ior(to -

Za e

.h.

..y M i.

c a

J..c'. ;3.*.e.1023:3.s.3 A 0' B,an 3.1,0. B,

.".gg' n

,n.

n 6 -'functi.,corei,3 (SRM'.,s sha

. be..r x

..3 g m,g g -

te'.r..a.ti s

M'dhall. e,i pe.alble,a..ci.its it.wo JSRM. 'w

... onal1 utron respons..'an. hereaf ter,

..est...ed.. d ' check ed

.,f.

. m m

m J.f<' for ne..

ra

..one in; hef qq.

  • We6fe Tjusdra6s%bere '. fuel;or W

p(fwhile ' required to :be ' operable,.

e. T M

f r. '

[7

"'$ codsrolsrodside 'Being " moved arid

% the'SRM'.s 'will be checked daily di.one tinithe'7ad fadent9ruadrant.-

' b for 1 response.;-

QFor3aritsRM 'to,2be : considered P-U-

fc11owing 9 -.

.,..2;c.M:ggy.y.,q M

~

A /&gp'erab1'e7Gh'e}ll be 'satisfled:

W@dif g:'/C~g. i,,

W. 'WW W -

-n

- L.'a.i; Q:.y:l. M. j.p?. O.. L..i condisioniiTsha

%F*F'f :.ae 9;A";yEfg}y.'?.f.ca'.,4 t

n'

.1: ' W :-W.- a

.y w.. <

) M, M_.$ 6'N N..,. h. M..' @ 4 N.$ 3;.ic e %y:

~ ' -

S' Amen ent:No ;M65 /. 6k :(3/26/80) r.,2 v

r~

~ 22%.. y@M... pin?. @N.p..!s:

s..

..Y a

3 '.

.V

f. $,"";m -

-,. s

~

.,M,.

v-

>,y.

"4 ^+. e

.;... - w... w.

. c.. -

MW PBAPS

.... [..

.m..w,.

..c. ;:...

S.W 9,.,

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.10.B (Cont'd)

-,.wg.4.10. B (Con.t.'d)'.l..[:'..,c.. 1 i

c; v.., ~, m :......v..

.;a..

...v....

N>...

1 a.

The SRM shall be inserted to

. g.c.,

,2.$, Prior:tofunloading or,.t M^,

reloadinii 6~f.1uel. as ' ' '

the normal operating level.

J.,' L.provided for.f.in sections.. ?

(U,se of special movable, dunking :. _.. < :

c.

m

, type detectors during fuel. loading.ti.:M,';d"/] 43.10.'B.2'.A U10.B.3, the 'Mdb gSRM'..s lshall dbe:(unctioriilly

y:0 and major core alterations.in place /gff@,p[.of normal detectors is Mte'sted;'I?Prid'r%td dnload-ing of.,ilso fie'checkedfuel.d.the SR b':E as long as the detector is connected..,.,

i to the normal SRM circuit.).3 6!. R t..i r should

'/.sh33p+Mp.fJ.Yor:~neutVo6'iresp'ons,e@S i

...e

.. s.y

^

Q.

.*May' beg..;:.. F.;;q 3;.g:..;.. y;'. p...

...Q s.&.

9 2

shall have a minimum of.Q-Q7:

.pa.gf y;f:..

~

lINSERTA_. b.

The reduceibpfoYided9'

~

j 3cp*withallI.pgis.fg11tingrfed

~ / y, inthe_corjs

.,. the SRM has an ob' serv'ed.

\\

)

.: count ' rate and signal-to-90%

Ine wr s.

hrfoise'fatio on or above iM Prior to unicamng or ruei, itated above';

3.he '~cdtve'shown on figuref N'^

/

z.

.SRM count rate may drop below 3 cps,-@e,.e!)%

shall be proven operable as fy3.3.1.V:.Fid55i 3 9.:.i.' r -"..... '7

'If#<i'-

I. p-p however, during unloading of fuel, th 7

=

  • y-l

.e-provided all control rods are full r;;A'

%: sg. Mde.iy" 4:t.A.

~.

3

7 c.....?, f @

Vr:vA "

i:.

inserted and rendered electrically :s*.. -..b.de.

~

  1. @.f inoperable with the exception of theI Md y.

,MR

.:9 9:

following provision. Individual' control.YO. ; nw;L

'/N,.,

V rods outside the periphery of the then M: '.

l/

~

existing fuel matrix may be electrically.

,o'rhaveiglcountratean

... signal 4ynoise ratio-armed and moved after all fuel in the cell

. '.#w'ithin 'th/TisiiM $f $iype" Y 2

containing that control rod have been removed from the reactor core.

-. :.b.ic., ;

3.3.1.

4:.- r'.

..: t.

. f
  • 4Z;f ys' 58g 3.,

Prior to reloading of fuel, two, three or 3

. h 4,-

four fuel assemblies may be returned to ?......

j, their previous core positions adjacent to pr' E ',:-/ ;e _. Qy)t~%

3,'

each of the 4 SRM's to obtain the required 'i.'

. n.f'... 45@ '.$' %

I 4

3 cps *. Until these assemblies are loaded,

.'.4,'i.M' the SRM minimum count rat.e is not required.

r l '-

fM q

%.q?

"... C "Ei.P.

.:J,h...i f.:,p;: 33

;.g, gh:/.e hi-

- 9,.:i dis iG?

5.}/.

The SRM minimum count rate is not required...

with all iuel removed irom the. core.t,$ ra;.?g' a

s
  • N.

ly:3,. *.

,- ":*'.3,,

.,5g.

fyp#W/D(p.M :d'%b"P.-%

...y l

During the unloading and reloading ef fuel' intermediate arrays of fuel shall alsa;)F%,

5.

,. h. :

j

!,t

. contain at least one SRM. l. %.',g.g

.j g

,.. 'S.!!.($N/h$N.'Nd:.h,., [,.

' j.f.Lc; 9..

i

"..dk..;'#bN#.

r w..,

gp?i?.h '

,e

. AM.i.tijGQ !"!:. :.~".i.(yg,C,;g6@h

'.:h $h

, :w G.. '.:... :).Y:pq1., :...; s r. m.'

p1 yr gytp;;~ :. f:,::;... ;n.'

p c

' :. ::..h::j.'E.5:* * &/.5.&'.:w l /

g 1

.. ~.

.. Q;;;.

hr.endment No. G4,149

.,.l.c ;. g.;G; t

O.,:...

,..W.. Y'9.q.g. !..

-W I:

l'.

August 28,1989

, -228 *f,

.i

,3 y

... ;k* *.

r.

~.

' '.., M.T.S.

l

i 1

- INSERT A INSERT B LCO 3.10.B SR 4.10.B (continued)

(continued)~

4. If one or more required SRMs are
2. Prior to performing core.

inoperable while in the refuel alterations, and every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> mode; thereafter during core alterations, verify an operable

a. Immediately suspend core SRM detector is located in:

alterations except for control rod insertion; and

a..The fueled region;
b. Immediately initiate action
b. The core quadrant where core to fully insert all alterations are being insertable control rods in performed, when the core cells containing one or.

. associated SRM is included in more fuel assemblies.

the fueled region; and

c. A core quadrant adjacent to where core alterations are being performed, when the associated SRM is included in the fueled region.

One SRM may be used to satisfy more than one requirement.

3. Verify that at least 2 source range channels have an observed count rate of 23 cps, or, are /

within the limits of Figure 3.3.1:

a. Prior to entering the refuel mode and every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter while in the refuel mode; and
b. Prior to performing core alterations, and every 12-hours thereafter while performing core alterations.

4

i l

INSERT B (Cont.)

SR 4.10.B (continued) 1

3. (cont.)

This requirement is not required to be met with less than or equal to four fuel assemblies adjacent to the SRM and no other fuel i

assemblies in the associated core quadrant.. Additionally, this requirement is not required.to be met during spiral fuel unloading.

4. Prior to entering the refuel mode, and every 7 days thereafter while in the refuel mode, a channel functional test and determination of signal-to-noise ratio shall be performed for each required SRM.
5. Prior. to entering the refuel mode, and every 184 days thereafter while in the refuel mode, a channel calibration shall be performed for each required SRM.

I l

t i

l

,...R -. m :ep.a.mnmgeq,s.y,n-.

' c.. g.,M." ?.'C.S. 0. g' ".M.... 9.y:".t,. f.

1."%.. Qnds2W F w..

e

. W. PC.W&,f,.

3.10 BASES (Cont'd) c, M..n : @. %. M.y.

The requirements"for SRM 0pera.11ty,during;the..i.gM.pm.,ltera.tio

%.. <.. ~.n

..w.. a

..p.

o1 se core a s assure W P.' A J J.

S.M.: pg:- ' m,.':%.n....:..,.. ?.W.m:Y.'.. :, yl

fil
:.

k V 4t sufficient core monitoring.

ch.

.ns..:

.....Q,.i:..:%aw.g..e.

s.,v...: :.e.

\\m:t.':qkt.'g.,,w3.r.. M

. m.c

-.<.~..a.3>.

n t.

.. q.s.

~ y.,:a. v,.

., pas.g

.~

e.

.0,.

Core Monitoring.... '.4

~.4.:r.n. %..:...vy g. p @ +W. n~ g;h.;. n v.

B.

4

.perio.dsiofi,r,ge c.~ :.m -kL.3' n deg# @.

m...-

>:ri.nM.wAv.. %.

n.

g

. v statio M

. shutdown and to guide the operator during r,,.uri.ng The SRM's"are provided to, monitor.tha core Requiring two operaole.ws.1n or to acentro3a,n,y[:, core -e W

quadran't'where fuel for contr.ols:iodsj.are.be.ing35vEd $si,)FeFa'd'(qEif station'startup.

u

.i W.3 counts, per secona^ provices assurance.tnat neutronif monitoring of that~juadrantiduYinF'.siic'Ti?,51,tirit)o$5'dMn

~

.:J.-

isib'siEgMMi$

\\

j -@M '

f@g D(W M.

~ " monitored. and insures Inst stertup's. is,id 15HhElc661.y.17 J.ne;sourcerBlfr'o~d'.drbP " "

conouctea onl an fluxleve'isabovetheminimumla.'dm s

...... accident. ' 9 M'@M$MMNNN% DMMMW

\\~

' b1;;ir

.P:w WQ. A.e!NW5 dod.during the Aguri[1g unloading of fuel,'.it ri.s[p,t. nq$si%t'o}du,.loE,the'M

.f

. -g ef al i,S,gi,'gduy.tRa'ti.. refuel mode and Since all. dis

[INSERTC_

fueij'o,ves.

ofJcounts. Vill'not. pre'sent a hazafd 1 ring core unloading v11

'to decrease below 3 cps.

t reduce reactivity, the_ lower number.c Requiring the SRM's'toWelfunctionally$ssfe'8p"fi' F.T6huirtremo' val @d-i _. /.. -

6 l

assures.that the SRM's.will be operableA.tathe star.tgfueM, removal he*

daily response check of the M.s ensuresjthelr3ontinue'd'6per.abil.ity

..m..,. 2,

,until the co unt.r: ate dimi ni s hes,:d. u.,..e.j,t.o.lfu..eT.;,f.r.e,m.,o..v Pa% %

w 2

~

k.1,.

s,

' cells 'from which all.f...e.e.l. ha. s.m.be.' periphery of the then e h.y.

d w

"W

.g..

gmatrix may b. icn.r r.e,i..o. u.t..si.de. the en. re u

e. armed ee'lectricall :andi

~ MF

.' n

,, M

' moved for maintenance'p'ufp. Tes9urilngg6eli.'r.

e'd :a'il ^ 'sW' i Af o

that control fuel are fully'.'inserf6d. add electr,ica'llyB '

f$

i

.i ?.\\..sF-:lb..Y.i Q ik.), W '? $ Q A &

.During core loading, the loading chad.1.acent,asse j.

s ;arou.nd.it L

T SRM's before attaining the minimum,c,ounj.;r. ate'of:,3,rps,*.y,is'ip' rmissible J 1,'F.g.g e

were removed and therefore will,. remsu.bcri.'tica.l,.co nf.i.gu.ra tpet t

  • OE$..

s ":e because these assemblies were. in 'a b

= o 1-

.s*,

D' v

sn =

t

.ai.,n. su.,tri. i,,c.a. y. e.n.;;...e. is amec f".a.4.<:44?.

LW assemblies are placed back into.the,1gyprevi.

l.h th p.

i y

gyj:..

n specification 3.10. A.2 requires that -all.co,o,us, posit, ions,.,' S e

G4 l

g l

ntrol gods >be :,. fully inserted 2. k V

' Y $ f&il & $ & Pi Q ' & Q h f5 & &

h. g.g.;!

ii.,prelilITdid durinb"ci~

Ng. ggf5-

' prior to loading fuel, inadv'ertent crjticality g 1oading.

. [ ':.

v f&

Soent Fuel Pool Water lavel '..'!}$'-

C.

The intent of the Technical Spec)fication is to

' co0erace for cooling and shiel' irWf aT.1.' times'M,prov,ide, adequat d

Witfitfe"w'Ete'rTitW

' levation 233' (its normal opei ating. level at the i

2 I

. s hey. hysical a.

.. e.if.l s ' edsi M ' 9 di M e

.S?sp ent f uel s to rage Jac ks...t._e r i. s.,ma'i nt..a.i.ne.d..ab..o

.t..o..r.%.y.,n. he,ue.;fg.,

'.l..

approximately 23 f t..of.w. a

.y

pool overflow to the skimmer,sur.ge tanks 'm o

.e gp ry'be

~ justed t.s.

h'tha 3fW.'

d

' minimum operatino water..l.evel.provides 22..f. tPo.ja e;.s.pecifi cati on 29 ;,c.g f:

ov cE irradiated fuel in the. storage acks.7s'For..th).

reason;g

.g

..r for minimum water co'verage has'.been e'stablish'e T &g.Y.W, d'a ihiF' YW.3i d ~ "1:h.r..:.'5. p.*yi.r.S.gia i.hk..$..GYi[W

,,v W:;W T Wi S

' provides adeeuate e r,,g..c...

< v.,,.W..,..,.,

.m,. pr. z,.,..,.

n. oi s e. f,,at o+are :,og.4..

.v

.ye n

e.,.
-.e., :.r ~.

. 3.r. g..

  • Ma.y be reduced provided the. coent rate and.s,:.y y t.,.o-..

g p.,.yy. 4.. e $

1gnal-

' ;. l.%,:..y C:.;:.5 Q Q:y; p,4; r

,. c. a. u...q.

. s above the curve shown on Figure o.o.l.

....q.ne3,.: ;l...

. 'o s.c. s. 3;

'WQ.%(.D.

" *:m.

.s-s.~

549 !. m.,.

y i'-h:

~r

.MM &.gg"f:.'W,*~Nl.4Wyi'ijy'Q

~"

Mp

- 0:

~

@@g %

t.

4. 231....U.,0 91.0. 5 ::.u:* IY.Y5t'.T.iY ' M D.y ;;g@n:

5 4

N NO Amendment i.io. 64, 124, 149

  • * *~'pfs'%.:-5.,Qy'U. *. * ?.th..@m g r ~p's e;&'O J

l y

.hM

..:.,..;x%-

.$$1g,,5:

Augeit 28, 198 j

l

-..m.;

t

.., 4.-/W[.l.i% [.P,9.: i,.s *: 2.GM/

,.9

~

  • I'~ '

...s

.+

.. (.l, l

i.

INSERT C SRMs are required to provide monitoring of reactivity changes occurring in the reactor core.

Because of the local nature of reactivity changes during refueling, adequate coverage is provided by requiring one SRM to be operable in the quadrant of the reactor core where core alterations are being performed and the other SRM to be operable in an adjacent quadrant containing fuel.

These requirements ensure that the reactivity of the core will be continuously monitored during core alterations.

In the refueling mode during an SRM centered spiral offload or reload. an SRM outside the fueled region is not required to be operable. since it is not capable of monitoring neutron flux in the fueled region of the core.

Core alterations are allowed in a quadrant with no operable SRM in an adjacent quadrant provided the requirement that the bundles being spiral reloaded or spiral offloaded are all in a single fueled region containing at least one operable SRM.

Spiral reloading and offloading encompass reloading or offloading a cell on the edge of a continuous fueled region (the cell can be reloaded or offloaded in any sequence).

4 4

I l

l l

l

water coveraga fer both shielding and ecoling at all times,.

. / including 'during fuel' movement.- The minimum water coverage p-

j. -

measurement.is the-distance between the top of the fuel red 9-plen'um and' the spent fuel pool water level at its lowest I. -

adjusted level.' With the water maintained at the. minimum level, there is sufficient water depth to ensure that any

-iodin'a released from'a hypothesized fuel handling accident would be reduced to acceptable levels before it reached the refueling floor.

There are no piping connections to the spent fuel pool at any lower elevation.

4.10 3 ASIS 1

~

,~

5.

Refueline Interlocks Complete functional testing of all. refueling' interlocks before any refueling. outage will provide positive indication.

~

j that the interlocks cperate'in the situations for which they i

were designed.'

By: loading each hoist with a weight equal to

- the fuel assembly, positioning the refueling platform and withdrawing control rods, the interlocks can_ be subjected to valid operational tests.

Where redundancy is provided in the logic' circuitry; tests can be performed to assure that each

. redundant lecie element can independently perform its function.

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  • Core Men' torine i

i' i

f Requiring the SRM's to be functionally tested prior to any core, alteration assures that the SRM's' will be operable at f l

j the sta'rt of that alteration..The daily response check o#

the SRM's ensures their continued operability.

7 i

=

Requiiing SRMs to be tested prior to and~during refuel mode provides assurance t' hat the SRMs will be maintained operdble.5 The weekly. functional test and signal to noise rati'o verification ensures their continued operability.-

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