ML20086D474

Proposed Tech Specs Re TS Upgrade Program for Dresden Units 2 & 3 & Quad Cities Units 1 & 2

ML20086D474
Person / Time
Site:	Dresden, Quad Cities
Issue date:	06/30/1995
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML17180B274	List: ML17180B273 ML20086D474
References
NUDOCS 9507100182
Download: ML20086D474 (79)

Text

,

i F011HFMUMID 0JLY DRESDEN II DPR-19 AmendmentNo.%,82 3.6 LIMITI$GCONDITIONFOROPERATION 4.6 SURVEILLANCE REQUIREMENT PRIMARY SYSTEM BOUNDARY

r PRIMARY SYSTEM BOUNDARY

'?

Applicatiliity:

, Applicability: _N

\\

x Applies to the operating \\

Applies to the periodic status of the reactor

\\

examination and testing i

coolant system.

requirements for the reactor coolant system.

Objective:

Objective:

1 To assure the integrity and To determine the condition of i

safe operation of the the reactor coolant system and I

reactor coolant system.

the operation of the safety devices related to it.

,/ ~

Specification: (.

SpectffcatTBn j

A.

Thermal Limitations A.

Thermal Limitations N

"g 1.

Except as indicated 1.

During heatups and N

in 3.6. A.2 below, the cooldowns the following

)([b M' 7

- temperatures shall be average rate of 2

ermanently recorded > at

,4 /

reactor coolant u

inute~ intervals:

temperature change

[n y

'~r~~~ reTctor VeiWsh

/ (O during nonnal heatup g/([c or cooldown shall

/

a

.4 not exceed 100*F/hr M"

when averaged over a b.- reactor vessel shell one-hour period.

flange N.

c.

recirculation loops -l A&B

~

-f

2..A step reduction in i 2; 1 ht temperatDres'lfitedt in 4.6.A.1 shall be j

temperature of 240*F )'

reactor coolant permanently recorded y

is pennissible so subsequent to a heatup

' or cooldown at 15 minute intervals until ]

long as the limit in Specification 3.6.A.3 below is met.

ghree consecutive

)

rqadings are within 5 )

degrees of each other.

y

[3 At all times, the shell

~

flange to shell temper-6.-

~

..)

-atyre differential o

h#_

g j

shall not exc 9507100182 95063o 3/4.6-1 PDR ADOCK 05000237 P

PDR N

F0E!F0HXD 0m DRESDEN II DPR-19

{

Amendment No. 114 3.6 LIMITING CONDITION FOR OPERATION 4.6 SURVEILLANCE REQUIREMENT 13f (cont'd.)

(cont'd.)

4 N

B.

Pressurization Temperatirre B.

Pressurization Temperature N1.

The reactor vessel shal 1.

Reactor Vessel shell 4[

K be-venteT and power N g ]

temperature and reactor 4,

operation shall not bey conducted 1niess the y g g' coolant _ pre _s.sure shall d>/

be germanently_.recorde' '

reactor' vessel ata15> minute intervals temperature is equal to whenever the shell y

or greater than that temgerature/isbelow shown in Curve C of g oP [6, gp) 220 F and the reactor /

- Figure 3. 6.1.

Opera-vessel is not ve jnted.

t tion for hydrostatic or

[ %"/ 7 leakage tests, during heatup or cooldown, and 30 with the core critical I '- ( l shall be conducted only A//9 '

when reactor vessel meta temperature is equal to or above that shown in theappropriatecurveof(

igure 3 6.1./FigdreT67.

is eff_ective through 16 effective full power M'

years.

At least six months l

prior to 16 effective full d'

power years new curves will) be submittede

~ ~ __ -

L r

2.

The reactor vessel head 2.

When the reactor vessel bolting studs shall not be head bolting studs are under tension unless the tightened or loosened fh5M c,4 g temperature of the vessel the reactor vessel shell immediately below shell temperature t

the vessel flange is

,j mmediately below the greater than or equal to

~

head flange shall be l,prQ(80 E.'

e

, Q(p 'ermanentlp recorded.

r FG l

3/4.6-2

$0RINFORMAll0I0ny

^

DRESDEN 11 DPR-19 Amendment No. /4, %,'87 7

a 3.6 LIMITING CONDITION FOR OPEPJ. TION 4.6 SURVEILLANCE REQUIREMENT.

.{

(Cont'd.).

(Cont'd.)

s

.3.

Neutron flux-

[

monitors and

~*

samples shall be.

installed in the l

reactor vessel adjacent to the vessel wall at th core midplane i

level. The monitor and sample

. program where.

p6ssible confo'rm j

to ASTM E 185'

\\../

he-mon ~ilors and

\\

g samples will be'

$tIk '3 removed and testcd

'I as outlined in Table 4.6.2 to experimentally-verify the gcalculated values of integrated neutron flux that i

are used to gs determine NDTT for 4

Figure 4.6.1.

f[M C.

Coolant Chemistry C.

Coolant Chemistry N

' Y' $ ~f.J

~

o

.i g

1.

a.

The reactor coolant 1.

a'. A sample of r actor activity shall be main-

. coolant shal be tained less than 0.2' taken a microcuries per gram every1)takt 6 hourj and DOSE EQUIVALENT _I-131 analyzed for DOSE.

y duringJteactor power)

'5d Yg 3 EQUIVALENT 1-131

[b. If the reactor coolant b.

When an isotopic

. activity is greater analysis shows than 0.2 microcuries reactor coolant per gram'and less than activity to be~l'n.

~

or equal to 4.0 micro-excessiof 0.2 3

curies per gram DOSE microcuries per s,

^g EQUIVALENT I-131, for gram and less than

.l more than 48 continuous 4.0 microcuries'per hours (one continuous I

gram DOSE EQUIVALENT time interval) an orderly I-131, additional-

~

shutdown'shall be<@ >~-

reactor coolant 3M

. e 3 (,(.

3688a

.\\

{5 3123A y3

FOR11F0EllID: 01LY DRECDEN II DPR-19 Amendment No. f.1, jf2, 87

,/

kb do t

/:

3.6 LIMITING CONDITION FOR OPERATION 4.6

, SURVEILLANCE REQUIREMENT (Cont'd.)

(Cont'd.)

y atlig initiated and.the b

,w sap 11 be C) unit shall be in old' dken and anay1

~

(d xhutdownwithin,24["ours. [~

at leastgt'imec s

N-ever 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

"\\

If a sample of reactor When reactor /

c.

coolant activity is greate\\

c.

coolant g

activity is greater than 4.0 microcuries per than 4.0 microcuries gram DOSE EQUIVALENT I-11,

per gram DOSE EQUIV-s 6 e 2 C sEmpIs'ishall'be 7

ALENT I-131, reaetor N taken and analyzed withjo '

coolant samples (f

( 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. dfl he second

' y,g, l \\

sample 5'ndicates a reactor

~

shall be taken and N., (

analyzed ever coolant activity greater hours until t e j

/

than 4.0 microcuries per j reactor is in a cold y

gram DOSE EQUIVALENT I-131,.

I shutdown condition.

an orderly shutdown shall /

g 1 be initiated and the unit 1PtcQtrepidshutdown (TT~ W~Vithin[24Jhourdu'1d

~

/

A the~ sic ~onii sample indicate

[areactorcoolantactivity

[3*

$ cfh

'Ib' g 6 4 1

less than or equal to 4.0

\\

f 74

[

microcuries per gram DOSE

/ j 3 (, d \\ y j

~

EQUIVALENT I-131, state-i 13

/ p '1 ment 3.6.C.lb shall appi p I 2.

The reactor coolant' During startups and at water shall not

[i,

steaming rates below j, f exceed the following (gh 100,000 pounds per g3g limits _with4tesmifig hour, a sample of pe ig d ates less than reactor coolant shall b 100,000 pounds per hoursandanalyza[r. hj be taken every ou hour excep as for 36 specified in'3.6.C.3:

conductivity and j V i

~

Conductivity 2' micro-mho/cm chloride content, hier13e To'n ppm

~

'3.lo'rheactor

a. E steaming ratec t

x 3.

the maximum value greater than or for conductivity equal to 100,000 [

shall not exceed 10 pounds per hour, af

~

micro-mho/cm and the W

reactor coolant f

pg(,b'f maximum value for Th3 sample shall be g

chloride ion taken at least y) b concentration shall every h hours.-att notexceed,0.fppm, when the' continuous for the first 24 N

,/ -

conductivity l

N

_l a '

i 3/4.6-4 3688a i

V FORINFORMAT10LONLY DRESDEN 11 DPR-19 Amendment No. J$. %, 87

-3.6 LIMITING CONDITION FOR OPERATION 4.6 SURVEILLANCE REOUIREMENT (Cont'd.).

( Co n t ' d.' )

."i4(/36%

[ hours after placing

. monitors' indicate 3'

p

- t c_raa&oM Jnhe abnormal conductivity, power operating ~

(other than' chort-

~

condition. j term spikes) and g

8 gg analyzed for conduc-p.

tivity and chlorid ion content.

~siieii'17FF ttmt1 ouc gM conductivity monitor y,G Ig is inoperable, a reactor coolant sample should c_.taken at leas 18 and analyz for q (, -

U5 h condu ivity and hlo de ion' con 4

Except as specified in 3.6.C.3 above, the reactor coolant water shall not L/6 -

exceed'the following limits with steaming rates greater than or equal to 100,000 pounds per hour:

Ot-M6EidLcEITrTty@ micro-mho/cm o

Chloride ion 0.5 ppm

[5.

IT Tpecification 3.6.C.1,l p 3 G U.

3.6.C.4 is not met, an.

'O'p.I 3.6.C.2, 3.6.C.3 or yp orderly shutdown shall be-initiated.

[e D.

Coolan i

D.

Coolant Leakage 1.

'Any time. irradiated 1.

Reactor coolant system fuel is in the leakage shall be y.4[

reactor vessel and checked by the sump g$

reactor coolant and air samplin gI' j

temperatu ov ystem.f Sump flow eactor

[ monitoring and-coolant leakage into f

recording shall be the primary f

performed once per-containment from 3,Ma (J) hours:. Air sampling 1

~

unidentified-sources t

shall be performed e

shall not exceed 5 i

4 once s,4.e.

g

~

3 a 0 % G<il l l '

FORINFORMAT0 DULY DRESDEN II DpR-19 4

Amendment No. J, p'2, 87 3.6 LIMITING CONDITION FO% OPERATION 4.6 SURVEILLANCE REQUIREMENT (Cont *d.)

(Cont'd.)

gpm.

In addition, the total reactor coolant system

, g.b p, (.

leakage into the primary containm p hall not exce pg 2 Q pyy If these conditions \\

V cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a Cold Shutdown condition p M' '

within 24 gy-r a

2.

Afterq 6m % tion of the

[

2.

The following additional i

investigation, or con-leakage limits chall be tainment inspection.

met until the recircula-

}

specified in 4.6.D.2.a tion piping indications or 4.6.D.2.b.

if the j

have been resolved.

leakage is determined

[

to be due to a thru wall Whenever the reactor is pipe crack on the reactor at operating pressure, coolant pressure boundary,;

the following will apply an orderly shutdown shall f

to unidentified leakage:

1. 'CL be initiated and the reactor shall be in a a.

If a 1 spm increase Cold Shutdown condition over the previous 4 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

hours occurs or when leakage equals 3 gpm total, an investigation of the cause of the leakage increase will be performed. This in-vestigation should consist of taking drywell air and water samples, and a review of any previous plant evolutions to the extent necessary to determine the source of leakage.

5

/

. '4M ' ', )

b.

If leakage equals 4 gpm, 9v a containment inspection D

will be conducted to determine the source of r

E.

Safety and Relief Valves

[ Safety 2 Rdief'VaTves 1.

During reactor power A minimum of 1/2 of all T5 operating conditions and safety valves shall be SGI i

whenever the reactor bench checked or replaced f

coolant pressurellt greater withabenchcheckedvalve/

-two,ro psig and tempey each reise11ogmes,;

/

3/4.6-6

(

l A

wM. }

y\\ Q^

,~

y,;

W

10HHEML0101Y DRESDEN 11 DPR-19 AmendmentNo.[,p#2, 87 3.6 LIMITING CONDITION FOR OPERATION 4.6 SURVEILLANCE REQUIREMENT

-(Cont' M.-) < 9 4

3 (Cont'd.)

h s

^

h a rt_320 *J all nine g ~Uie safety valves shal e popping point of the of j bg ^

~

safety valves shall be set be oper.able f The so1 N id h pD

/ activated pressure valves as follows:

{ shall be operable af required Number of Valves Set Point f by Specification 3.5.D.

(Psig) f 2

4 2

1250 p-

egM,

[

6 d

b s ~6 y(o The allowable set point error pc for each valve is plus or minus 1%.

m All relief valves shall be 3 pr')

checked pressure each te flisling_nutage. The set pressures shall be:

2.

If Specification valve No.

Set Point (psin)

/

3.6.E.1 is not met, l(@

')Nfy an orderly shutdown 4e 203-3A 1124*

shall be initiated

1. (-

203-3B 1101 i

and the reactor d

coolantpressur3_.andf 203-3C 1101 203-3D 1124 tieniperatur6 Tall b'eD 203-3E 1124 less than or equal to 90 psig and less than

• Target rock combination safety / relief valve.

1. L- -

or equal to 320* F d

The allowable setpoint hM l within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> i

error for each valve is plus or minus 1%.

F.

Structural Integrity F.

Structural Integrity

'M-.

The structural integrity 1.

Beginning November 1, of the primary system 1978, and updated every boundary shall be 40 months thereafter, maintained at the level the Component inservice

@ jk' )/

inspection program required by the ASME Boiler and Pressure Vessel Code.Section II, M'g shall be perfonned in ACCordance With Section k

" Rules for Inservice XI Of the ASME Boiler Inspection of Nuclear and Pressure Vessel T

Power Plant Components"

\\

Code and Addenda as Components of the

^

N required _by_10_CFR 52, primary ::ystem boundary

~

eC 6 50.55a(g),'

whose instrvice eXCept where specific o

written relief has been examinatio1 reveals the

)

given by the NRC absence of tic

/

i ications or flaw /

pursuant to 10 CFR 50, )

eCtion 50.55a(g)(6)(i)/.

/

-s 3/4.6-7 3688a

e F0m' F0M0:]ONLY bRES0ENII DPR-19 k.endment No..J4, 54, 82 3.6 LIMITING CONDITION FOR OPERATION 4.6 SURVEILLANCE' REQUIREMENT '

-(cont'd.)

(cont *d.)

-W

-indications not ia ex. -

cess of the allowa.51e -

indication standard > of this Code are acceptable for continued service.

Plant operation.with components which have inservice examination flaw indication (s) in excess of the allowable indication standards of the Code shall be subject to NRC approval.

/

a.

Components whose inservice examination reveals flaw indication (s) in' excess of the allowable indication standards of the ASE Code,Section XI, are unaccept-

?

able for continued service

-(5 #de 6 unless the following requirements are met:

(i) An analysis and ~ eval-uation of the detected flaw indication (s) shall be-submitted to the NRC that demon-strate that the com-ponent structural in-tegrity justifies con-tinued service.. The analysis and evalua-tion shall follow the procedures outlined in Appendix A,' "Evalua-tion of Flaw Indica-tions", of ASE Code,Section XI.

(ii)

Prior to the re-sumption of service, the NRC shall review the analysis and

.j evaluation and s

3/4.6-8

_i-________.__

{h D SD nt No. jlf, 82 3.6 LIMITING CONDITION FOR OPERATION 4.6 SURVEILLANCE REQUIREMENT l cont'd.)

(cont'd.)

either appr resumption of plant 1-operation with the affected component l

or require that the l component be

[

repaired or replaced.

b.

For components approved for' continued service in accordance with paragraph "a" above, y%

'O 4 P/

reexamination of the area containing the flaw indication (s) shall be conducted during each scheduled successive inservice inspection. An analysis and evaluation shall be submitted to the NRC following each I

inservice inspection.

The analysis and evaluation shall follow the procedures outlined in Appendix A,-

" Evaluation of Flaw Indications", of ASME Code,Section XI, and shall reference prior analyses submitted to the NRC to the extent applicable.

Prior to resumption of service 1

following each inservice' inspection',

the NRC shall review the analysis and evaluation and either approve resumption of plant operation with kf~

3/4.6-9

~

F0'WF3M' 00 DNLY DRESDEN II DPR-19 AmendmentNo.%,82

~

3.6 LIMITING CONDITION FOR OPERATION.

4.6 SURVEILLANCE REQUIREMENT-(Cont'd.)

(Cont'o.)

the affected component or require that the component be repaired or replaced.

E 'j/

c.

Repair or replacement i,/

of components,

/

including

. p *c reexaminations, shall p "g conform with the requirements of the ASW. Code,Section XI.

In the case of repairs, flaus shall be either i

remved or repaired to

{

thu extent necessary to fifG'p/

\\

meet the allowable l

k irdication standards j7 7.o,p specified in ASME Code,Section XI.

-?

N w

G. Jet pumps-Aw G. Jet Puh 1.

WheneverJe_ Reactor i 1.

Whenever there is i

~

g indhe'Startup/H h recirculation flow wit StandbyorRunmodes,1 the reactor in the -

/

all-jet pumps shall~

StiiTuji/H6titandb,y_.or n

i be intact and all Run modesWet pump

/p )

operating jet pumps Tiiteg~rTty and

+

shall_be operable.

operability shall be

{that a jet pump is (3)'

verifying that the h

f it is determined A-a checked 45 fly by inoperable, an following two orderly shutdown conditions do not shall be initiated occur simultaneously:

S,/ g and the reactor shall

'I k

be in.a Cold-Shutdown ~

o condition within a'.1e r.ecirTulation f -{pW" g

pump flow differs v

24) hours, by more than 10%

from the Lj~$

f established speed-flow characteristics. /

s..

~

3/4.6-10

r_-__-__________

701 IN0bF-"----1TlDilDHY

~ - -

^ ~ " ~ " " ' " "

l 3.6 LIMITING CONDITION FOR OPERATION 4.6 SURVIILI.ANCE REQUIRENENT (Cont'd.)

(Cont'd.)

The ind core flow is more l

than 10% greater P

than the core flow y4 g'('g value derived from established Power-core flow

~

relationships.)

indicati 2.

AddlM cNally wh

-f ' /

Jj g

each of the twenty operating with one

),{

recirculationy,4 th jet pumps shall be p'4 p 6

he equallYe' valves verified prior to r

initiation of reactor closed, the diffuser to startup from a cold lower plenum differen-shutdown condition.

tial pressure shall be checked _da11 N W

/ M.c rfnIITarprJN1hre>

/ of any jet pumps in the

,{g,/

' idle loop shall not d (

vary by more than 10%

'& kW frem established pattarns.

75LS f ru B.2 V

3/4.6-11 3688a 3123A

Qp.j%[13ULiiNi[a MN-lY DRESDEN II-DpR 19-h [9 y Lg,[

!U h Us).b I

'AmendmentEs.g,

, 95 e

9 3.6 : LIMITING CONDITION FOR OPERATION

.4.6 SURVEILLANCE REOUIREMENT

-1 (Cont'd.)

(Cont'd.)

3. lDuring Dual Loop 3.

The baseline data l'

' Operation,'the indi-required to evaluate cated core flow is the conditions in the sum of the flow-(

Specifications 4.6.G.1 l

indication from each

\\

and 4.6.G.2 will be of the twenty jet pumps.

N acquired each operating During single Loop cycle.

Operation (SLO), the indicated core flow must be conservatively

[

adjusted based on L

statio G n procedures.

p

('4. If ilow indication failure occurs for t 6' 3 gb[p[ d ct' i

or more jet pumps, inunediate corrective g-g e action shall be taken.

If flow indication for

~!

all but one jet pump cannot be obtained within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> an S

orderly shutdown shall 4 pf

'g,C

]

d

~be initiated and the reactor shall be in a

/

\\

cold shutdown conditio grithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

H.

Recirculation pump Flow

',Eecirculation pump Flow j

Limitations Limitations

]

1.

Whenever both Recirculation pumps speed recirculation pumps shall be checke are in' operation, for mismatch.y) pump speeds shall be maintained within 10%'

of each other when power level is greater y

than 80% and within 15%

of each other when

' 3 6[ 3'b'C power level is less

'C0 i

n s0%.

M 2.

If specification 5

3.6.H.1 cannot be met, Dg.3, G,C one recirculation pump

[tr/Ed j)

-l shall be tripped.

3/4.6-12 3688a

-l

'3123A

f:

54 J.

l.-.

.e A.

4 4

a A

FH3!F)HMT 010"LY DRESDEN II DPR-19 Amendment No. 127

' i

' i e

'l

~

l l

[

g THIS PAGE INTENTIONALLY LEFT BLANK i

l

)

3/4.6-13

[

5:s

,j DRESDEN II DPR-19 Amendment No. 127 l

e P

3 h

I 13IS PAGE INTENTIONALLY LEFT BLANK l

N N

)

I i

l 1

3/4.6-14 J

I pgM3310AT10E 30.Y DRESDEN II DPR-19 Amendment No. 127

]

3,6 LIMITING CONDITION FOR OPERATION 4.6 SURVEILLANCE RE0VIREMENT (Cont'd.)

(Cont'd.)

~3FDuring Single Looheration\\

Q. Deh-for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the following restrictions are c

m required:

(T5@ % A. Ack.W~

/

a.

The recirculation pump in the idle loop shall ro rom starting b D "E M ' A 'O

except to permit testing in preparation for retu ning to service a b.

The flow biased RBM Rod Block LSSS shall be

)

h'sp34A,At-Ll.c')

reduced by 4.0%

/

LSpecification3.LCelf; c.

The flow biased APRM Rod w

Block LSSS shall be y y, (,. A, K /.c--)

reduced by 3.5%

/

C cation 2.1.B); /

d.

The flow biased APRM l

scram LSSS shall be 6i3 uD 3 (, A ' Ah Lc

)

l reduced by 3.5%

(Specification 2.1. A.1);-

C ~ TS MCPR Safety Limit

,A,A h D ;

shall be increased by Q

0.01 (Specification 1.1.A);

f.

The rated flow MCPR p 3 4,g, gap Operating Limit shall be increased by 0.01 (Specification 3.5.L.2);

I 3/4.6-15 i-

i j

li DRESDEN II Amendment No.12pPR-19 i

LIMI"D G CONDITION 'FOR OPERATION ~

4.6 S1JRVEILLANCE'RE0VIREMENT

~

(cont'c. )

(Cont'd.)

i g.

The MAPLHG Limit shall be reduced "3WP 3,b 4 * (yG Ms by the appropriate r

multiplicative factor from the Core Operating i

Limits Report-S ification.3.5 h currenuy one Au omatic Pressur,e Relief Subsystem relief l

valve is out-of-service, 'o the MAPLHGR Operating Limit shall be reduced 1

by the appropriate i

multiplicative factor from the Core Operatin Limits Report.

i g

',6 4.

With no reactor coolant system gb recirculation loops in 5

i ess-than'1!5%_ thermal reduce core operation of w(thTii 2~

urs and plac Mrate 6-power to unit in4ct stmtdo_wn within the (following 47(hours.

- 2 Y q:

5.

Idle Rehulation Loop Startup

!Ke Recirculation Loop Startup, An idle recirculation pump shall The -temperature differentials and flow l

not be started unless-the rates shall be determined to be within

}i temperature differential between the limits within 15 minutes prior to the reactor vessel steam space tartup of an idle recirculation loop.

/

coolant and the bottom head drai tlina coolant is less than or equal to 145'F*, and:

~

[T~~When both punips have been ~

({

vu./44.S idle unless the temperature

/

diffe,rential between the -

reactor coolant within the idle loop to be started up and the coolant in the gg 34.bl reactor pressure vessel.is-j less than or equal to 50*F, k

Wloo a 3Mz.

[ T When onl'Yess the kamperature has been u f f-

1. P idle un gu diffe,rential between the f

"St[

e/B

/

O reactor coolant within the idle and operating recirculation loops is less f-than or equal to 50*F and f

thes$eedoftheoperatin$

pump % of ratedyJpeed._ [~

s less than or equa to 43 I.

Snubbers (Shock Suppressors)

I.

Snubbers (Shock Suppressors) x.3 The following surveillance requirements apply to safety related snubbers.

to g pplicable with reactor pressure vessel steam space pressure 1 25 jisig Q 35 4 N

3/4.6-16 2

3.6 kTNITING CONDITION FOR OPttATION 4.6

$URYTTLt.ANCE REQUIREMENT (C:st'd.)

(Cut'd.)

X j

1.

During all modes of 1.

Visual Inspection operation ex9e'pt cold shutdown and' refuel, An independent visbal all safat related inspection shall be snubber shall be performedonthe[ safety' operab e except as related hydrauli mechanical snubb,e and noted in Specification ers in 3.6.

.2 through 3.6.I.4.

accordance wit the schedule bel y

]L I k a.

All hydr ulle 1

l

. \\l

, Li snubber whose seal 4

I materia has been

(.

demons rated by opera ng j

exper ence, lab goranalysis['

test to b compatible wit the operating any ronment shall be isually in pected. This in pection shall i(clude,butnot n cessarily be I mited to,

! inspection of the ydraulic fluid

}

eservoir, fluid onnections, and I

/

inkage connection ph

'to the piping and i

t anchor to verify g/4.gf anobber operabilitr-b.

All mechanical snubbers shall be.

visually inspected. This inspection shall consist of, but not necessarily be limited to, inspection of the-snubber and attachments to the

. piping and anchor for indications of damage or impaired' operability.

3/4.6-17 3688a 3123A 6 '-

AmendesstNo.14,p,95 4

3 f

i

[3 INITING CONDITION FOR OPERATION 4.6

$URVIILLANCE REQUIRENENT L

(

(cent'd.)

(Cont'd.)

)

No. of Saubbers j

Found Inoperable Next During Required

)

L Inspectio Inspection 1

Interva Interval l

0 18 months plus or minus 251

~

1 12 months plus or minus 251,

2 6 months plus or minus 25%

3 124 days plus or minus 25%

6.7 62 days plus or minus 25%

or more 31 days plus or minus 25%

i 1

The required inspection interval i

shall not be.

1engthened more than one step at a time.

I Snubbers may be J

categorized in two groups, "acces-sible",or."inacces-l sible," based on j

l their accessibility

)

for inspection j

during reactor operation. -These j

two groups may be i

inspected indepen-dently according to the above schedule.

2.

From d after the 2.

Functional Testing time

'anubber is a.

Once each refuel-

{

detep ined to be inoperable, continued ing cycle, a re/ctor operation is representative plraissible only sample of approxi-uring the succeeding mately 10% of the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> unists the hydraulic snubbers snubber is sooner shall be function'.

\\ made operable or ally tested for d.

erability. inc1 d-3/4.6-18 3688a 3123A

~

7 1

-pu p 3/</, 7 F

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f

~~

w u,,,s., u

.f wra-6, Amendmelt No. P. yt, 95 c

11 e

3.6 ' LIMITING CONDITION FOR OpttATION 4.6 SVEYWILLANCE EE0VIREME (Cont'd.)

(Cont'd.)

I (1)

Activationf (restraining action) 14 1

withinty[e achieved

\\

specified range ofvelofityor acceleration in botht/nsionand j

comprehsion.

]

(11) snubb r bleed, or r lease

-rate / where

-i required, is wit in the spe ified range in ompression or tension.

Fo each unit

[

an subsequent un t found p[

idoperable,an i

3h g,f a ditional 10%

o the hydraulic s ubbers shall I

, tested until o more allures are ound or all inits have been bested.

\\/

b.

Once/ each refueling cycIe,a-

}

representative sample of.

Approximately 10%

lof the mechanical snubbers shall be functionally tested for operability.

The test shall consist of two parts:

3/4.6-19 3688a 4

3123A J

%, p.-19 Dpt Ii g

DtXSDEN II 95 Ame.% ee N3.

e 3.6 LIMITING CONDITION FOR ' OPERATIOJ 4.6 3URVIILLANCE REQUItr.nini--

(Cont'd.)

(Cont'd.)

(1)

Verification that the force that initiates freej movement of the snubber in either tension or 'ospres-sion is 1 s than the speci led maximum eskaway friction force.

(ii) Verify het the activa ion (re -

stral ng action) it achie ed within the spec led range of acce3eration or velopity,asappli-cable based on snu ber design in bot tension and e

ression.

For es h unit and subse eat unit found inope able, an addi-

[^

tions 10% of the p

mech leal snubbers-

- (A t shal be so tested untill no re failures are 3/4 b f fou or al1~ units have bee tested.

c.

In ddition to the re lar sample, snubbers; wh ch failed the pr vious functional test sh 11 be retested duringI the next test period.

I 1( a spare snubber has l bpeninstalledinplace of a failed snubber, then both the failed pnubber(ifitis j

tepaired and installed !

in another position) anci the spare snubber shall!

be ratested. Test results of these snubbers may not be included for the resampling.

h 3/4.6-20 3688a 3123A

/

,,.~

DRESDEN II.

DPR-19 3.6 LIMITING CONDITION FOR OPERATION 4.6 SURVIILLANCE REQUIREMENT (Cont'd.)

(Cont'd.)

3.

If the requirements 3.

When a'enu e is of 3.6.I.1 and doene noperable, 3.6.I.2 cannot be a rey ow of all met, an orderly pertinent facts shall shutdown shall be conducted to initiated and the determine the snubber i

reactor shall be in mode of failure and to cold shutdown or decide if an

-\\

refuel condition.

engineering 1

within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

evaluation should be i

\\

performed on the i

supported system or

\\

components. If said evaluation is deemed necessary, it will

\\

determine whether or not the snubber mode of

\\

failure has imparted a significant effect or degradation on the supported component or system.'

4.

If a snubber i 4.

If any snubber.

determined to e selected for functional inoperable 11e the testing either fails to reactor is n the lock up or falls to cold shu own or

move, i.e.,

frozen in refuel mode, the place, the cause will snubber'shall be made be evaluated and, if operfleorreplaced determined to be a pript to reactor generic deficiency, st rtup, all snubbers of the same design subject to the same defect shall be functionally tested.

\\

\\

N

/

E 9

0 4

- 3 /.4. 6-21 V

3688a 3123A gre e

DRESDEN II DPE-19 H

'1P J-Ameldme t No. fl. N 95 q

]di

.Eh, 5

i

$URVIILLANCE REQUIt ytMENT

~

[/G_LIMITINGCONDITIONFOROPERATION 4.6 (Cont'd.)

(Coat'd.)

5.

snubbers may be added 5.

snubberf ervice life or removed from monitating shall be safety related systems foJI'owedbyexisting j

without prior license tation record systems,

\\

amendment.

including the central j

'N filing system, h

maintenance flies, safety related work packages, and snubber inspection records.

The above record

.sh retention methods shall be used to prevent the 1

N hydraulic snubbers from exceeding a service

\\

life of 10 years and

\\

the mechanical snubbers from exceeding a service life of 40 years (lifetime of the plant).

1 I

\\

/

S' t.

l

!~

3/4.6-22 3688a l

3123A

\\

~

^

FOR11F0 HAT 0" DIU "A

N DRESDEN ))

DPR-19 N

Amendment No. 123 MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F)

/

1600=

E E A - systru NyonoTEst uuit CURVE A_

E wrN rUEL m vcssn

• "' E i

s - NoN-NUCLEAR HCATUP/

m'M i N 8

C cootooww uut.

c 1400i v^uo To 16 uPy i.c-stew

/ b'l/

/

f i

/ N

/

O 5

[

b BCLTUNE:

En

• ff---

12 82*F 6

i f

f' j

8 i

////

/

/

~y.

s i

///

l. /

F 1000E 9

H/.

t 800 ;

s e

i j

l iE 600 $

l l

t-i l

l

=>

3 5

w b

/w 400!

/

N HON-SCLTUNE

" No,.e r

/

m esc e

=

r i

/

/

I f

/

I 200 -

E BOLTUP

,w r g

/

=

0= unnin union uunin inuun unuui unuui

ununi, n

O 50 100 150 200 250 300 350

-3 MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F) h

/

(ptd g u. P

)

'* Q j 3/4.6-23 g(,aA

7 FORINFORMATION ONIJ QUAD-CIIIES.

'L1R t j

3.6/4.6 pR1HARY SYSTEN BOUNDARY LIMITING C0t#DITIONS FOR orttATION SURVE'.L L At CE REQUIREMENTS Applicability

'A Ilcability:

I Aeolles to the operatlag status of the reactor coolant system.

Applies to the periodic examination and testing requirements for the reactor Objective:

coolant system.

To assure the integrity and safe opera-Objective:

tion of the reactor coolant system To determine the condition of the reactor-coolant system and the operation of the

/

safety devices related to it.

SrECIFICA110N$

A.

Thermal timitation'.

l.

Except as indicated in

(

6 Specification 3.6.A.2 below, the N4 During heatups and cooldowns the

~_qsaF~ age, rate nf reactor coolant N following temperatures shall be

, g. ed e ~ '

fem 6erature change during normal y

.j (permanently _recogetat b__/p,p5=Inuteintervals:

[g b,

heatup or cooldo-n shall not 1

,e p exceed 100*F/hr -hen averaged

-f' 41%p

/)

over a 1. hour period.

/

a.

reactor vessel shell,

'l 3 I b

go f)

/

b.

reactor vessel shell flange.

and l

g\\ >

I~2.

recirculation loops A and_Bj c.

A step reduction in reactor

-C~

=.

coolant temperature of 240*f is 2.

The temperatures listed in

}

permissible so long as the limit Specification 4.6.A.1 shall be r' { y In Specification 3.6.A.3 below permanently recorded subsequent f

.\\.

is met.

to a heatup or cool.$own at s

N

]

15-minute intervaP, until three w

consecutive readings at each g,,/

given location are within 5

'p--

degrees of each other.

3.

At all times, the shell flange Q

{

to shell temperature differential shall not exceed 140

• f./

t d.

The recirculation pump in an (die recirculation loop shall l

nat be started unless the coolant in tha' loop is =lthin

.( lSt4? 3 4'D "

1 I

50'F et the operating loop L4 0 T

coolant t g erature.

J l

3.6/4.6-1 Amend +ent tJo. 127 y

y

/"

p 3

/ '~~

I Pressurization Temperature

'\\ k

..)5 B.

Pressurization Temperature D

1.

Reactorvesselshelltemperatureand/

Q' ~~~(evented and jower 5p_shall_be 1.

The_ reactor vessel s

s R'

eration.]

\\

'Nh.reactorcoolantpressureshallbeRmanent shal Fhofbe~co6 ducted unless 7%

C* %

intervals whenever the shell the' reactor vessel temperature ;

M is equal to or greater than r

temperature is tiliw'220.*FaWth0 C g; G j rlac~to[ i~isil is J o_t_venfe~d g p9 thatshowninFigure3p1 e

s b

-m Neutron flitirmonitort and samples-2 Operation for hydrostatic or leakage tests (Curve A), during shall be installed in the reactor

_.s vessel adjacent to the vessel wall heatuporcooldown(CurveB),[

at the core midplane level.

The

]j3 A p or with the core critical w )

(Curve C) shall be conducted l monitor and sample program shal (onlywhenthereactorvessel J conform _to_ASDLE_185-61/TC temperature is equal to or

/

monitors and samples shall be (E.,d N removed and tested in accordance 1

' above that shown in the

/

appropriate curve of Figure /

Q@ O -

with the guidelines set forth in 4 3.6-1,JFigure 3761 lFm 10CFR50 Appendix Hfto experimentally 1 s

[ veYIff'the7alcuTited values of frective through 16 EFPY. At integrated neutron flux that are

)1 Y,

least six months prior to 16 /

, EFPY new curves will be /

used to determine the NDTT for

~

< submitted.f Q igure 3.6-1 7

'2.

ih'e"reictir^vds'eUhNdbl ting i.'When the~ reactor vessel ~ head boitliigN studs shall not be under ifN studs are tightened or loosened, the )

'T tension unless the temperature u.c6 reactor vessel shell temperature j

T5 % h [

of the vessel shell immediately dmmedlitely below the head flange S _al'I'be rdersiIedi > recorded.

hj below the vessel flange is 2 /

-;E, h

'~

G. ' Coolant Chemis Q 100*F.

i

-~'

I C.

Coolant Chemistry \\

\\

~~ N x

1.

a.

A sample of reactor coolant

)

y Thesteady-stateradiolodine')

~

m shall be taken at least every 1.

/,

%houT1Pand analyzed for concentration in the reactor coolant shall not exceed (5 H T M,. ~

x' radioactive iodines of I-131

/

through I-135_during power pCl of I-131 dose equivalent s

x per gram of water.

j % j M [9 woperAtlon.JIn addi~ti_on, when mLL " "

[chimneymonitorsindicatean

)!

X \\~

'~

increass in radioactive gaseous

[/

p,

~pCl/sec. whichever isefflife~5 gec L/c 7 tM

/

greater, during steady-state 3 6.7, U c

' "'~~j

'f,p,'?4T)I

~

reactor operation, a reactor d0 n N coolant sample shall be taken

~~

and analyzed for radioactive lodines.

j

~ ~ ' ' ~

~

r.

' b.

An isotopic analysis of a " ' N reactor coolant sample shall be\\

gRr7v-made at least once per month. y g%_c,_

y ;

yc

- 2.

Whenever the steady-state N

f radiotodine concentration of

\\

[ b q % I;i ' N[ \\

.~

prior operation is greater than )

b3._-

3.6/4.6-2 Amandment No. 127

J.',

M

~

' QUAD CITIES DPR-30.

.isd G44\\},1~~y"'d.'pr3h nr y

UIJ

[

than 10% of Specification -

3.6.C.1, a sample of reactor coolant i

shall be taken within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of any reactor startup and analyzed f for radioactive iodines of 113

/

through I 135.

4

, go '

L

]

6gy i

V

~

d h

.}

y

< /,

3.6/4.6-2a Amendment No. 47

.. a

r g.

DPR-30 I

(throer,h1431)

d. WheDne steady state ra-p2 diciodine concentration of prior 3A'gi

'Peration is greater than 10% of th Specincation 3.6.Cl, a sample t;f -

reactor coolant shallbe taken prior so any reactor startup and ana. -

lyzed for radioactive iodines of c-I-131 through I-135 as well as the coolant sample and analyses re-aguired by Specincatio 4.6.C l.c I

%~

above.

(_

2. The reactor coolant water shall not exceed the following limits _with 19, l1. During startups and at steaming rates.

p 3

below 100,000 lb/hr, a sample of reac-for coolant sha!! be taken every 7' %pdj

',3 sicasiingratesjt]ss Ean,100,000lb/hr) 3 M~ 3 oncept as speciAeR5'pecindo hours and analyzed for conouctivity /

vity 2 pmho/cm h NI PP*

n

[.

3. ' For reactor startups, the maximum.

3. a. With swiing rates greater than (

value for conductivity shall not cacced or est to 100,000 lb/hr a reac-pMf

~

10 pmho/cm and the maaimum

\\

value for' chloride ion concentration tor wolant sam le shall be taken s

at least every(9 hoiirs and when b

shall notenceedffppm for the Arst 74%ues af\\er placing the reactor in the condnuous conductivity moni-nors indicate abnormal conductiv-vyicsifirpeisting condido~D - -

. ley (other than short-term spikes) ] Q".3

( W'and analyzed for conductivity and]

(4 g 4*Escepanpec15ed~ifSpeilicaii6

1. , ~ 3.6.C3 above, the reactor coolant s-

\\

" 8"

~

water shall not esceed the following b.' When the continuous conductivity limits with steaming rates greater than tpek y -

or equal to 100,000 lb/hr:

/

monitor is inoperable, a reactor h

coolant sample should be taken at i;;q conduedvity 10 pmho/cm N

""*I **d I*'**"~

N 7' I

/

ductivny 3 and chloride ion -

7 sidon'de ion 1.0yp3s consent.

3 It s'pecificitio'n~3TCl, 3.6.C2.

p(]l c

3.6.C3 or 3.6.C4 is not met, an or-k derly shutdown shalthelnitiated. -

p

' @ Coelas Dtil A D. Coolant 14akasel

1. Any time irradiated fuel is in the reac-Reactor coolant syssem leakage shall ser vessel and reactor cooltat tempera.

auttisbove 212' F,7Eactor coolant checked by th.3_ swap,andair umpHag system.

N j,

Sump flow monitoring and recording

~

p,3 fig leakage into the primary containmem p

Dom unidentinedyutstuhalLmot-shall be performed once per(shffD o.

exceed 5 gpm.,1n addition the total Air sampling shall be perfor:ne seactor coolaiin system leakage into the once per

~

y

~

g;7.

7 ~ '

pnmary contamment shall not cacced j L %j y

25 pm.

~

r2.6 s i t L.-.4 3

Q5A a N4H K-U ~$ <

3.4/46-3

+

Amer.dment No. 59

F0 WF0 EAT 00BIM

~

QUAD-CTTIES DPR-30

'2.

Both the sump and air sampling sys. )

M tems shall be oprable during reactor /

power opradon. From and after the i

date that one of these systems is made at found to be inopreble for any sea.

son reactor power opradoo is pr.

missible only during the succeedin5

- ' ' f

~

2. irinte.or.dico.s ircrsa]above.an.

LS.-

t

~

g

,o>.

not be met. an orderly shutdown shall be initiated and the reactor shall be in

. &//#' y p' Nga 7~

a sold shutdown condidon within'@4

/

7 g{'

b=c'-

mf.

E. safer; and~kelief Yahee 1 f safety and Relief Yahes I. Prior to reactor startup for power op-A minimum of I/2 of all safety valves

!! be '

eration. during reactor power oprat.

bench checked or replace <Lrith bench ing conditions and whenever the r-ac.

checked valve eachtriTusling outage). The pop-l nor coolantyressure is.greaterfiri9'0' -

ping point of the safety vakes shall be set as

'y;, n 3A ( b (s.

pti(knd temperature greatetthan4 follows-t

.,320' F/liinine of th valres Q ~Mbe aperaklesf senvated pressure valves shall be oper.

t e solenoid.

Number of Yahes Serpoint fysig)

\\

,7 required by Specincationj I

Il35m l

2

'/

2.

T$peci5 cation 3.6 E.1 is not met. the 4

1260 reactor sha!! remain shut down until the condition is corrected or, if in The allowabic setpoint error for each valve is 75 gcg operation, an orderly shutdown shall ~j ENk d h m MP 115

"'~

be initiatedlariflhe reactor coolant tessure and temperature shall be f G

[ *g*ch 'f"'lin8'**t83*'Th' 888 Prusures 88 L

Qw, 90 psig

~h.>J u n, -,

Member of Veher. :=

f

' Serpent (psig) t-

' f 4 34 2

51135 Qrrarget Rock combination safery/ relief valve.

F.

Seincratellatsgrity

- F. ~ Sermen M (

j.

I The uructural hiegrity of the,premary system The sondestructhe hspections Isted as feb

,4. ///

.,. M boundary sha!! be maintained at the level n.

d.s.1 aball be performed as specifad h assor.

k-.qn q

guired by the ASME Boiler and presane Yeas!

dance with Secties XI of the ASME Soder and/

/

(' eLNuclear hwet_Eant f- -'"7W14. Code. 5setaos XI. " Rules for harvice inspecties Preanne Vesel Coje '1971 Edition. Summeth d

i 97143de'adt he resuhs obtained from som '

J Edstion. Senmer 1975 Addenda (ASME Code plianae with this specificaties wel be evahasted Esaios XI).

w aher 5 years and the noechmons wCII,e revtewed

^

/

Qtth the NRC.

y v

n s yod

~

j

+

S,s td.s d knendment No.

, 80 r

c

- + - -

a DPR-30

+

p Components of the primary system boundary whose inservice examination reveals the absence of flaw indications or flaw indications not in ex-cess of the allowabh indication standards of this r

Code are acceptabh for continued service. Plant operation with components which have inservice examination flaw bdication(s) in excess of the allowable indication standards of the Code shall be subject to NRC approval.

Ng

1. Connonents whose inservice examina-tion reveals flaw indicationP.) in excess of the alawable indication standards of

{

Q< 0 g i

~

the ASME Code, Sectioa XI, are un-acceptable for contimv.d service unless the following requhements are met:

\\

a.

An analysis and evaluation of the detecaed flaw indication (s) shall be submitted to the NRC that demonstrate that the component j

structural integrity justifies con-j tinued service. The analysis and evaluation shall follow the pro-cedures outlined in Appendix A, "Evahation of Flew Indications",

of ASIE Cods,Section XI.

I

b. Prior to the resumption of service, j

the NRC shall review the analysis

{

and evaluation and either approve I

l resursption of plant operation with the affected component or require that 6e component be repaired or replaced.

2. For components approved for continued service in accordance with paragraph 1, reexaminstion of the area containing the flaw indication (s) shall be con-ducted during each scheduled successive inservice inspection. An analysis and evaluation shall be submitted to the NRC fotowing each inservice inspection.

The analysis and evaluation shall follow the procedures outlined in Appendix A,

Evaluation of Flaw Indications", of ASME Oxle,Section XI, and shall

\\

reference prior analyses submitted to the NRC to the extent applicable.

\\ each insweice inspection, the NRC shall Prior to sesumption of service following

~j q

3.6/4.6 4a Amendment 32

FOR INF0K A"l00 0'JLY QUAD-CITIES DRP-30 s'

review the analysis and evaluation and either approve resumption of plant operation with the affected component I

or require that the component be re-i paired or replaced.

]

.f

3. Repair or replacement of components, including reexaminations, shall conform

~?

j 90*{

with the requirements of the ASME

[

j Code,Section XI. In the case of repairs, j

flaws shall be either removed or repaired L

to the extent necessary to meet the allowable indication standards specified in ASME Code,Section XI, m

3.6/4.64b Amendment 32

OP -30 ebu d

t Pbmis'Nw G

s

[1.

Whenever the reactor is in the Whenever there is recirculatiort g sfD X' Star. tup / Hot _ Standby:or-Run

' g,ip flow with the reactor in the modes, all jet pumps _shall_be_)

Sta7tilp/EStandby_or_Run_mDo y'

~-

intiiEt?and all operatingjet jet pump integrity and h', --

pumpsJhalLbe_operabled If it gb

< dilly' by verifying that two of operability shall be checked 6!9 is determined that a jet pump is inoperable, an orderly the following conditions do not

\\ ccur simultaneously:

shutdown shall be initiated and

~

Q the reactor shall be in a gold'.D bm

\\

shutdown condition withind!4;_

a.

The recirculation pump flow

~U hours.

differs by more than 10%

~m

/

from the established

-/p f 36 h qp'j.4 Sy>

'Mpeed-flow characteristics /

Tb b.

Theindicatedtotalcorex\\

flow is more than 10%

_s

, -g g,0 Q) -

greater than the core flow \\

u

(

value derived from

,o \\

established core plate l

' ~,, p A c NDP/ core flow relationships,

'Th"

-- Z L m

N c.

Individual ~jit pump flow for

/

any jet pump differs by more

[A @ {

than 10% from established

)

flow to average loop jet

)

g3 p

8

(

[^

\\-_.__

~

f 2.

Additionally, when operating with w-2.

Flow indication from(19 of the l

one recirculation _pumphiT1Fi the 20 jet pumps shall be verified

-equalizer valves closed, the q

prior to initiation of reactor diffuser to lower plenum startup from a cold shutdown differential pressure shall be condition, v checked daily /Ofid~the x\\

' differeliTTil-pressure of any jet i

\\

pump in the idle loop shall not M*

y

(,

(d W vary by more than 101 from '-

established patterns,.

(3..

2-l

~

The baseline data required to u

3.

The inditsted core flow is the evaluate the conditions in s

sum of thq flow indication from

\\

Specifications 4.6.G.1 and each jet pump with operable 4.6.G.2 will be acquired each flow indication.

In addition, l

operating cycle.

for any jet pump with I

inoperable flow indication, the flow indication frc1 the companion jet pump on the same jet pump riser shall he summed a second time to compensate for the flow through the jet pump with inoperable flow

/a Ifflowindication[

\\

indication.

\\f ailure occurs f or three or 1631B/0600Zs d.6/4.6-5 Amendment No.121

Q DPR-30 Tmortjet pumps?immedTitex corrective action shall be g keny If^ flow indication fo Illut two jet pumps tannot be pq*76& J obtained within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, an t /

orderly shutdown shall be

/

g~ tie'In'a'<61iD shutdown condition initiated and the reactor shall 7....

(LP wIlhin'24' Iiours.

M g3, 4._

If flow indication failure occurs for both jet pumps on

(,thesameje.tlu_mp_rtser,famediate corrective acti_on; p

(indicattorFforatleastoneof shall be takeff71ow the jet pumps cannot be obtained within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, an i

orderly shutdown shall be kg'be1nT1 cold > shutdown condition initiated and the reactor shall gp t

5.

If flow indication failure '

is d 1g/

m' I

occurs for both calibrated (double-tap) jet pumps on the tame recirculation loop,_

h lanediate~ correct 1WEEtioP shall be taken.[ ff fl~oT i

~

Inditatrorrfor at least one of the jet pumps cannot be obtained within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, an 73 orderly shutdown shall be f )j initiated and the reactor shall

~

W

(_bFinac6Tdshutdownconditionj wi thirif2fliours.

g v

/ c, s

H.

Recirculaflon Pump flow Limitations H.

Recirculation Pump Flow Limitations 1.

Whenever both recirculation Recirculation pumps speed shall be pumps are in operation, pump checked daU y>for mismatch.

speeds shall be maintained N~ ~ ' m~D

)

within 10% of each other when

(

Ok power level is greater than 80%

c$nP) and within 15% of each other l

when power level is less than 3.G c/

80%.

W

~2 N if~5pTclfication 3.6.H.1 cannot D be met, one recirculation pump / '

3" shall be tripp A e *'

2 y 16318/06002 3.6/4.6-Sa Amendment No. 121

4 T; ;"'

FOR11F0HATID101Y 7-w N

,3. During Single Loop Operation for more than e

I l

' 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the following restrictions are I TS '* 3 A ' b ired:

a. The hlCPR Safety Limit shall$

(72 ut 16 M ' j increased by 0.01 (T.S.1.1 Alu'

__/

b. The MCPR OWa~ tin ~g Limit, as specified Uup 36.h hL^/6 in the CORE OPERATING LIM TS REPORT, shall be increased by 0.01 (T.S. 3.5.K)>;.e ram and Rod (c7The floV

)

Block Setpoints shall be reduced by 3.5% to read as follows:

y p f },b. A, h

• j/, c T.S. 2.1.A.1; S t.58 WD + 58.5 T.S. 2.1. A.1;

• k S 1(.58 WD + 58.5) FRP/MFLPD T.S 2.1.B; S 1 58 WD + 46.5 T.S. 2.1.B;

• S 1(.58 WD + 46.5) FRP/MFLPD T.S. 3.2.C (Table 2.1-3);*

APRM upscale 1(.58 WD + 46.5)

FRP/MFLPD

'l

)

F A, h* /, ]/

In the event that MFLPD exceeds FRP.

f

d. The flow biased RBM Roc Block 7gb setpoints, as specified in the CORE OPERATING LIMITS REPORT, shall be reduced by 4.0%.

CThe sciicuiatiim pump inIliidWloopy d

A k (.

shall be electrically prohibited from T{ -

sqp 3 starting except to permit testing in preparation for returning to service. j m

d 3.6/4.6-5b Am,endment No. 143

R 60E E E C?)W PR-30 With no reactor coolant system ]\\g 1g Acc.s2,

~~-

^

~

~

4.

recirculation loops in In-^-

M f m 6 %s s

reduce core _ thermal operation power to less then 15% of V )

rated within'L2 hoursMd place /

the unit in hot shutdown gi'J a~g

/.ngd22hbiJrs.J within the fo110w1 x

,5.

Idle Recirculat~ ion Loop 5.

Idle Recirculation Loop Startup h

Startup The temperature differentials and An idle recirculation pump flow rates shall be determined to be shall not be started unless within the limits within 15 minutes

')

the temperature differential prior to startup of an idle

/

between the reactor vessel recirculation loop.

in cokant ffm$eadhan is less than or equal to

(

,# l

,145'F*, and:

me gog

[

When'bo'th pumps b (3Iy>

~

~

s been idle, unless the l

temperature differential between the reactor coolant within the idle i

looptobestartedu$e

,b.I

)

t and the coolant in t w

reactor pressure vesal t

i 3 is less than or equal tg

~

T ' When only one lo been idle, unless the N

\\

temperature differential between the reactor coolant within the idle and operating (p

recirculation loops is o F *p 3.c. o. z.

less than or equal to 50*F and the speed of the operating pumps is

{

1ess than or equal to 45% of rated pump speed.

{

l l

r~"'

l

N j-h 30b,Lo M

'Only applicable with reactor

-[ R pressure vessel steam space pressure 2 25 psig.

.)

\\

\\

3.6/4.6-5b(1)

Amendment No. 143

r 2 AD-CITIES

.' [

OPR-30

\\

. I; Shock Suppressors (Snubbers)

I.

Shock Suppressors (Snub s)

The following sury ance j

requirements apply to all snubbers o safety related ping. systems.

1.

During all modes of operation 1.

Visual spections shall: be except Shutdown and Refuel.-all perfor d in accordance with.t e snubbers on safety related follpwing schedule utilizing (he piping systems shall be operable acc ptance criteria given by f-except as noted in 3.6.I.2 5 cification 4.6.I.2.

t following.

j 2.

From and after the time that a Number f Snubbers L

snubber is determined to be-nd noperable Next inoperable. continued reactor g Inspection Required

]

operation is permissible durt uring Inspec-Inspection 1

the succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> on1 if n Interval-Interval the snubber is sooner mad

/

operable.

/g 0

18 months

)

+25%

3.

If the requirements o 3.6.I O

~

and 3.6.I.2 cannot met,[n 1

12 months orderly shutdown s 11 ben

+25%

initiated and the reactorti all be in a cold sh down cbn tion 2

6 months within 36 hour4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

/

125%

(/

4-If a snubber it de ed to be 3.4 124' days inoperable whil t

actor is 125%

in the Shutdown.

uel mode, the snubber shall made 5,6,7 62 days operable prior to eactor 125%

startup.

y,8 31 days 125%.

The required inspection interval shall not be lengthened more

.i than one step at a time.

i Snubbers may be. categorized in j

two groups, ' accessible' or 1

' inaccessible' based.on their accessibility for inspection during reactor operation..These y

two groups may be inspected independently according to the above schedule.

I

)

12ELc cAq D u

h U ? ]f0, 16318/0600Z 3.6/4.6-Sc Amendment No. 121

fbfkh i

.]

/

1 QUAD-CITIES OPR-30 Snubber service life Itoring shall be followed by e snubber surveillance inspect n records and maintenance his ory records. The abov record.

retention method hall be used to prevent the ubbers from exceeding a se Ice life.

2.

Visual inspe tions shall verify:

a.

There re'no visible indic tions of damage or impa red operability, and b.

At achments to the f undation or supporting tructure are-secure.

3.

Onpe each refueling cycle a r presentative. sample of 10% of e total of.each type of.

snubber in use in the plant shall be functionally tested either in place or In a bench test. For each snubber that does not meet the functional test criteria, an additional 10%

of that type of snubber shall be functionally tested.

4.

The mechanical snubber functional tests shall verify:

a.

That the breakaway force that initiates free movement of the snubber rod in either tension or compression is less than the specified.

maximum force.

b.. That the activation 1(restraining action).ls-achieved within the specified range of N

acceleration in both tension-and compress 1on.

y-y L%o 3/4 7 F i

a'

?

11788 3.6/4.6-6 Amendment No.111 l

l

1&

r N

x QUAD-CITIES s

DPR-30

>/

5.

When a snubber is deemed !e inoperable, a review shal conductedtodetermineth)emode b

of failure and to decide' if an engineeringevaluation/shouldbe

~

performed. If the en ineering evaluation is deemed necev-sary, it will deter Ine whether or not the snubber e of failure has impar ed a significant effe t or.

degradation on e supported component or s tem.

~

6.

If any snuche selected for functional t sting either falls to lockup o fails to move, i.e...froz in place, the cause' will be e luated and if l

determine to be generically deficien all snubbers of the same de ign, subject to the same l

defect hall be functionally teste.

7.

In a dition to the regular l

sa e, snubbers which failed the previous functional test sh I be retested during the n t test period. If a spare s bber has been installed in ace of a failed snubber, then th the failed snubber (if it s repaired and installed in i

another position) and the spare snubber shall be retested. Test results of these snubbers may not be included for the resampilng.

$AD hN55 l

W 4

.5

~

11788 3.6/4.6-7 Amendment No.111

L CITIES L

[. #

DPR-30

,/

PRESSURE LIMIT AS A FUNCTION OF VESSEL HETAL TEMPERATURE

/

1600_

! A - SYSTEM HYMOTEST UMIT CURVE A j

WITH FUCL M VESSEL E 8 - NON-NUCLEAR HEATUP/

m 52'%

B C

OcLTUNC J

3 cooLoowN uuiT.

v^uo To is ErPY r

1400E f

j I C - NUCLEAR (CORE CRITICAL) j f

j 3

UMff, VAUD TO 16 ErPY r

i

^o l

~/

12 W

scount:

/#

8 -

12 82*F s

s 14 87'F I

[

16 91'F h

l F 1000; d>

I r

9 i

/#

(

/

th

=

e 800

{

6 8

r I

j j

s t

x 5

E 600!

f f 1:

E 5

2 i

AJ N NON-BELTUNE 5

m NOT d

5 312 PSIC

/

/

f j

w b

l l

200 E

f E

80LTUP

/

g soo'r j

I

/

/

/

5 0

ininui unu ui unuus ininui unuiu unuiu uni lu 0

100 150 200 250 300 350

/

METAL TEMPERATURE ('f)

MINMUM-REACT N

FIGURE 3.6-1 pp qf,.

y I

F s u fE 3 4.K' L

- k d

Amendment No. 127 l'

l 4

x

'>3 i

TABLE LIl N

IllSERVICE 1RSPECTiell RE0lilREIIENTS FOR tuASCITIES

,- e,

,we,e<N 1

IIsted Ensel.stina to Enemised

\\

A Langitudsel and cir.

e: list applicable with I

cumlerental shel present plant des' n g

welds h core region

- 8~

Longitudmel and ck.

Voir..rc Durmg each 10-year Accessbie top 10 feet of i

cumferential welds in

\\

inspection interval vertical vessel weld in two -

\\

(fr 10% of places (100% inspected h 10

.l shes (other then those of cateswies lonitudmal yews for approximately 2 feet A and C) and meridio-wid 5% ek.

en rdueleg outage) not and ekcumferentiel tiel length i

seem welds h bottom se, )

i head and classe head (other then those of 10% of meridional seem welds b Category C) vessel closme head and 5% of crcumlerent' l welds in vessel e

i closwe head 4

J

.\\

Note: Bottom head closwe not applicable with present plant des' n j

E C

Vessel-to-ilenge and Volumetric Cumulative 100% cov-Equivalent to 10% of vnsel-to-head-to-gence ek-wage at end of 10 flange and head-to flange j

cumferentist welds.

year interval Skcumlerential weld are a each.

refuelig outage-

\\-

D Primary nouir o-vessel Volumetric Cumulative 100% coverage Nonie welds:

s and non h-head welds.

at and of 10-year hter-R%'aculation outlett: once and aan -to-vessel, va!

every 5 ysars Rectculation' inlet o: at t

nonh-head hside least ance escli ling -

red' section outage t

Core spray hiet : once every 5 years'-

Control rod drive retural:

once every 10 years Standby liquid controll once(

j every 10 yews

\\

Head hstrumentation: once \\.

l r

/{

every 5 years 3)

Head sprey biet i once evey t

4.

10 years e}A, Q,o

3.6/46-16 j

i.,

...c-.

,/'

j p

t,-

/

1ABLE 431 (Cast'd)

Campuset Parts to Essaisettes Fregossey of totesery be Essedeed Ilothed Esselsettes Examisatiess!

E Partial ation Vaual The exambations per-The area surro g each welds hcludsit con-formed dwrig each penetration 11 be examined trol rod drive inspecten interval fur ev~ ce of leakage durrig penetrations and shall cover at least pre e testrig vessel hstrumenta-25% of each group of tion nonles penetrations of com-parable site and functon Safe ended nonles:

F Prrnary noules to Visual, surface, Cumulative 100 safe and welds and ' volumetric erage at end 10-Recrculation outlet : once 2

year sterv every 5 years

!O Recirculaten inlet : at once each refuelmg outage t

Core spray inlet : once every 5 years g

l Control rod drive : once every 10 years Standbfy quid controll:once eve /10 years 2

, instrumentation : once ever(5 years 1

Head spray inlet : once every 10 years G1 Cbsure studs and nuts Volumetric and Cumulative 100% eqverage 100% of vessel studs and nuts visual or surface at end of 10-year hter-will be inspected each refuel-val ing outage Ligaments between Volumetric Cumulative 100% coverage Equivalent to 10% of ligaments threaded stud holes at end of 10-year inter.

(ach refuelrig outage.

val Eltamination of bushings, threM, and ligaments in base material.cf flanges may be performed om the face of the requ'ed to be flange and r

examined only the conne;-

tion is dsassemb Vaual Cumulative 100% coverage Equivalent to 10% of ashers

/,Closwe washers, bushaigs at and of 10-year hter-each refueling outage, hings val not appleable with present f

/

des (n.

Pressure-retsbrig Vaualand Cumulative 100% coverage Equivalent to 10% of rec' culat-r bolteig ;t2 hch volumetric at end of 10-year hter-hg pump bolts each refueirig

(;j dierneter val outage.

3.6/46 17

[73tt/

U.c.G i

y;cgi ies m L,Eht' W

/^h ut t

i t

y' -

/(

x'

/

\\

tastg 4A 1 Igent's

/,

y %,,

'N

,,e,,,,,,,,

geespry to fasedmed\\.

listed Essadasties Essadastenst

\\

G2 Presswe-retabhg N' Visual Cumulative 100% of cow.

Bottmg will be examined when boltag <2 hch wage at end of 10 yew bolths is removed,or when the diameter interval bolted connect i broken or g

For mg which is not or where the bolted

\\

connection is not broken, the inspection will consist of a visual examination to detect sens of distress or evidence of leakhg.

H integrany welded Volumetric Dw' 10-yew interval 10% (approximateh 8 ft) of vessel supports imeal feet of vessel support sk't weldhg in 10th year, s

i Closwe head claddag Visual and Durmg 10-year hterval 9qring the 10-year interval, swface or at best sin patches (each 36 in 3,,gth distrb r

the closweh.uted in volume ic N

7 aual Durmg 10-year hterva!

6 patches (each y) evenly V

's Vessel claddag distrbuted h the accessbie

/

sections of the vessel she'lN

,/

shall be examined, s

f w

/

/

,s ae 4 o c '>

j,

(,..)

3.6/46-18

r "07 ?H 0 B' T10i;' DI M' iL i'

QUAD-CITIES DPR-30 TABL.E 441 (Cast'd)

/

gespasset Parts to Essadssues Fregssser of caessary totassesse meses tassessess Esandssuessi f

J Ce'caulerental and Vausl and Cumuletive 25% of al uWt 2 longitudsiel pqm -

volumetric weld joints (selectively Pipe 1stal welds die use distrbuted among the System

. des Wolds 2 et the end el' mis hgher stress joints ki

{

isWe ter a M, enthe system) overy 10 Shutdowrt years.

cochng' 20-in.

17

\\

el mese wou J RglC 3-h.,4-in.

33 Group I and Group 11 Jteactor welds (See Note 1 for

/ water locaten breakdown) on /'

cleanup 4-in.,6-in.

27 man feedlines and main CRD hydraulic

\\

steamimes shall be/

system 3 in.,4-h.

18 inspected in 10 years RHR 16-in.

29 dwing the kperiod.

Head spray 4-h.

28 At least 25% of the welds Core spray shall he' inspected at ppng 10-in.

- 32 approEknetely each HPCI 10-in.,

14-in.

24 Feed 4-in.12-in.

/2. / -year interval.

Group welds shall be p5hg 18-in.

inspect wing each Recrcula-10-year perlbd there-ten 4-in.12-in, after.

Main Steam 22-in.,

22 h.,

28-in.

135 3-h.,20-h.

120 K-1 Inteersty welded Vaual and 100% cumulative h first Welds to the presswe-

! volumetric 10 years

. tainns boundary, the enternal support attadiments for pip.

25% cumulative h each metal beneath the weld ing, valves, and following 10-year h-zone, and along the support pumps spection hterval attachnkt member for a distance of'two base metal thicknesses,

'l K2 Support members and Vaual 100% cumulative dwing Support setthes 3

structw/for pip-each 10-year hspection stant and variable type mg,vsdves,and hterval hangers, snubbers, absorbers shall be inspect' punps whose i

strIIctwat bitsgrity to verify pro,1er detrbuten of des' n loads among the e

setied upon to withstand desen leads associated support components.

and seismic-hduced deplacements.

[]"

L1 Pump casst welds Vauel and One pump of each type Not appicable with present s

vobmetric damg 10-year interval plant desh.

,, '/

3.6/46-I9

w__,

Y J

FOR OF0HTE DRY DPR-30

,s fasts 441 leset'd) essessant parts to Issadasten pregesesy of smessey toEssedsed itseed ganadaseen Essedusesasi L2 Pump casess Vous!

One pump of eachtype One recirculateg pump h

'N dwing 10-yew htervet 10 years.

\\

il dasssembled

~

f Weids h vek Visual and One velve of each type Not appleable with present M bodes 3 hches aml veh, metric dwing 10-you intevel plant desgn above M-2 Valve bedes 3 inches Visual One volve of each type One disassembled valve (with or andabove dwing 10-yes htuvel withouIt welds and 3 inches over il disassembled br1Iurmel sire) h each category

'and type sher be subject to visual exammation.

Individusi sommation shal cover 100% of the pressee -

bounday welds and may be periemed at w near the end of the 10-year intaval.

/

eg irst refueling Intwim twfaces and htsmal ou$g)and dwing sub-N Interior swfaces and Visual (not components of the reactor htemets and htsgraNy inservice sequ refueling vessel, hchdmg the space at meided stamel supports inspection Code) of the reacter vessel, ages at pimeteh the bottom head and htsmal meludag care spray

. 3-year intdivals attachments which we welded sporgers, core spray coules, and upper to the vessel made accessbie portions of jet pumps by the removal of components dwing normal refueling operations.

Al htamal attachments whose may adverseh elect htsgrity shal be examined.

O Control red drive Vebmetric The examsetens The sher hclude the weld metal s'(base metal for one houshg presswe-performed di, ting each n

,eis m wenis.

hs,ecihn his,v.i wei -

beyond ti. edge shal hclude the el tie weld.

welds h 10% of the peripheral control y

rod drive houshes.

.s,es 1.

EM Insehetens d

d.i mhie es.mt man,im strwt eimmets m a nnen, w he. tans a inewn e emit.eismen te nen). i, wm om,m.a, pone a the==

csweery appeammstely ee.ust to t8use WWteu sammes. h the e.ent further unacceptchie structwel Wiscts are rev

- (,,,!

r es,e,,,..e.emme te me e.i - m oi -. setee.,

t(8 3.6/4 6-20

pr, i.

L h-

QUAD-CITIES

/

x f

x a

148LI 4.51 (Ceefd)

/

j 2.

Category 1 Weld Greakdown f'

Male Steelsbee. Group troup 11 Welds Wou Wo mes Line setion telt !

Line cetten tielt 3001A 20.in.

30A 520 30Af 3001A.20.m.

30A 310 30A. 4 i

524 30018 20 m.

308 310 p18-20-m.

3001C 20 m.

30C 510

-F25 30010 20-W.

300 310 308 F28 3001

-W.

30C 321A 30C-F22 J

30C-F25 30010 20-300-521 J

300 F22 300 F25 Feedwater Une troup i Welds 11 Wolds

/

Weld idestill-Wifi-Lies setles telt 2 setienh 2 3204A 18 in.

32A 34 3204A 18.in.

32A $1 3204814 in.

328 35 32A F6 32A.11 3204818 in.

328.F4 328 F7 3204C 12 in.

32C-52 3204012 m.

32D 52 320 56 3204t 12 in.

32EF7 320 32 3204F.12 in.

32F 52 32F.F6 3.

Suppleanetel inspection Progrese ter First sad Second Reluellag Ostages a.

The followag critcal sensitiled components shall be mondestructively enemmed by the methods mdcated.

C,en/

sement E=mmateWethat -

wens el leW4eplaced sete4nds P1 and uff or1111 base materet for at least one 6 The mess subsett to summeh she4 include 100% of the etterer sortaces of the welds a ttom 1. Weld aroes to be emmmed wet thdates beyond the edge el the meld, i

[ Secten XIInservce As memastens shoe be senducted in accord with the suemmaten techaques and procedures and meet the acceptance standards specified in the s.

keepecteo Code and sepplemented where escessary by specel technques with demonstrated capability to detect stress 4strosen crackag

/

d.

The mesheten trageancy shall centerm to the telleurmg schedole

/

Somotelhe welds of leid4eplened selo4mds 11 25% st a withm the trat reiveing estese 2) 25% et er withm the second refueima estage Jn the n set spy at the ammmetens ter item 4 rneel indestens of structvrai selects whch upon weiusten resure repers a replacements

/

e fehe4 he subfect to pones by the MC.

')

/ %

f gy u,u.u

q l

Idhnij k D'R-l

- s QUAD-CITIES DPR-30' TA8LE 4.6-2 N

l r'-

/ N REVISED WITHDRAHAL SCHEDULE FOR QUAD-CIIICS UNIT 2-Hithdrawal Coments.-

Year Par (No.

Lp tion 4Iall - 2150 1

1981 18 2002 17 Mall - 950 0

Standby 19 Hall - 245 15 Hall - 650 Standby 20 Hall - 2750 Standby 1979 14 Near Co 0

Top Guide 90 16 Near Core N

l 1981 0

/,/y Top Guide ' 180

/

,y, uf 3.6/4.6-21A Amendment No.127-

h'b l'I I

ab.

QUAD-CITIES.

I i

DPR-30 7

E

~.

?.--y

\\

NN i

h I

Y h

I i

=

I S

hW5

\\

i

/

'SR R

R R

R E

(3.) 091 + 10N '3Hn1YW3dW3113553A WODY38 i q]r FIGURE 3.6-1 MINIRJM REACTOR PRESSURIZATION TEMPERATURE

\\

iY

\\-'\\

x's Q

-/

s N N s 1000 s

/

x x

/

/

,00

/

~

t

\\

'E i

io oE. f y

\\

FAILURE "C

o.

w -4 o

1.0

\\

5 glimit Established for C1 at Operating 0[ Concentration =0.3-0.4 ppm m

mE EG 8

/

N g=

g 0.1

=

NO FAILURE

[E

-, m m

C-i k

mg

{

8=

\\

/

m o"

0.01 p

/.1 1.0 10 M

M 0

W mQ

~

n B

CHLORIDE (ppm)

C E

C

E3

~

m m

~

M

-4

/

i ATTACHMENT E Marked-Up BWR/4 STS Pages l

l 1

i l

l i

l e insop\\tsagrai 36

t F011NO[R E 0f; a y 3/4.4 REACTOR COOLANT SYSTEM T[RECIRCULATIONSYSTEM I

RECIRCULATION LOOPS LIMITING CONDITION FOR OPERATION h)%.T~1(Two reactor coolant system recirculation loops sha r

.3.

?

5

.hoscm F

s i

/

APPLICABILITY: OPERATIONAL.CONMUQNS 18 and 2H ACTION:

9

^

WithIone reactor coolant system recirculation loopg[iYoperation i J-- 1.

A firmidiiti1F~ihitiate measures to_ place _tlii~iiniCliLatjenst HOT SHUT g ' g within_the-next_12 h gosf P.'%

With no reactor coolant system recirculation loops in operation, immediately initiate measures to place the unit in at least STARTUP withifn-hours and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

(D (c r With a pump disch'~rie bypass valve inoperable, verify the valve to b

( % _ closed at-least once per 31 days.) g a

/

SURVEILLANCE REQUIREMENTS

/

l-

/

G 4:1Q1'.T3) Each pump discharge valve (and bypass valve) shall be demonstrated

~

OPERA 8LE by cycling each valve through at least one complete cycle of full travel during each startup** prior to THERMAL POWER exceeding 25% of RATED.

b'{hh]ERMALPOWER.e TH

/

/

)

TlIEach pump MG seg scoop tube mechan'cal and electrical stop shall be 4

rs54~(120)%7respectivelyT6f ratid coFi pojntsAess than or equil to (112)DA demonstrated OPERABLE with sverspeed set flow,}atTeas~t once~ pef 18~siiinths.

s.

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"See Special Test E'..

.ptio 47 o

o.

• • If not performed within the prev.f ous 31 day's. j r

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v~d y/ 3 24 @pp' k At SL4 @unAK t

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f J. &a e /A] WuG 5

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I 3.4.1.1; Two ' reactor coolant : system recirculation loops shall be in peration with:

I Total core flow greater than or equal to 45% of rate core flow, or a.

b.

THERMAL POWER less than or equal to the limit spec l'ed in Figure 3.4.1.1-1.

APPLICABILITY: OPERATIONAL CONDITIONS 18 and 28 ACTION:

a.

With one reactor coolant system reci lation loop not in operation, immediately initiate action to reduc THERMAL POWER to less than or equal to the limit specified in Fi re 3.4.1.1-1 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and initiate measures to place the un in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

With no reactor coolant syst recirculation loops in operation, immediately initista action reduce THERMAL POWER to less than or equal to the limit specifi in Figure 3.4.1.1-1 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and initiate measures to pia the unit in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT. SHUTDOWN wit n the next 6, hours.

c.

With two reactor cool nt system recirculation loops in operation and total core flow les than 4SK of rated core flow and THERMAL POWER greater than the 1 it specified in Figure 3.4.1.1-1:

1.

Determine APRM and LPRM** noise levels (Surveillance 4.4.1.1.3):

a)

At est once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />,-and b)

Wi hin 30 minutes:after the completion of a THERMAL POWER rease rf at least 55 of RATED THERMAL: POWER.

2.

Wit the APRM or LPRM** neutron flux noise levels greater than th times their established t>aseline ncise levels, immediately i itiate corrective action to restore the noise levels to within he nquired limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> by incraasing core flow to greater than 455 of rated core fisw or by reducing THERMAL POWER to less than or equal to the limit specified in Figure 3.4.1.1-1.

• See Spe tal Test Exception 310.4.

• • Detec r levels A and C of one LPRM string per core octant plus detectors A and of one LPRM string'in the. center of the core should be monitored.

.\\

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4

- _ _ _.. -_ _ ________ _ ___-__ _ _ _,1

=..

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REACTOR COOLANT SYSTEM Pr pr e.,.,

JI" SURVEILLANCE REQUIREMENTS *

/

4.4.1.1.1-Eachpumpdischakgevalveshallbedemonstrated. OPE LE by cycling each valve through at least one complete cycle of full treve} during each startup* prior to THERMAL POWER exceeding 25% of RATED THERMAL POWER.

4.4.1.1.2 Each pump MG set scoop tube mechanical and 91 tricil stop shall be i

demonstrated OPERABLE with overspeed setpoints less tkhn or equal to 105% and 102.5%, respectively, af rated core flow, at least ce per 18 months.

~

4.4.1.1.3 Establish a baseline APRM and LPRM**

utron flux no'ise value within the regions for which monitoring is required ( ecification 3.4.1.1, ACTION c) i within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of entering the region for wh(i h monitoring is required unless baselining has previously been performed in he region since the last refueling outage.

i

.)'

l i

not performed within the previous 31 days.

tector levels A and C of one LPRM string per core octant plus detectors A and C of one LPRM string in the center of the core should be monitored.

ff;,_A L

1 3/4 4-2

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3/4 4 3 4

9

fr%r rnciniES QukD s '#d h f REACTOR COOLANT SYSTEM JET PUMPS k:

LIMITING CONDITION FOR OPERATION Y*~DN11 jet pumps shall be OPERABLE.f~---(./aadfic "iEderIm, delile atX

'li 3.

o j g.,,,y ffgg,.y o <*!

/

picdG6; )

APPLICABILITY:

OPERATIONAL COND$T10fiS-1 and 2.

ACTION:

~]d 64 IAM U

h With one or more jet pumps inoperable, be in at least HOT SHLITDOWN withir.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

3: 3 I ' U. ;i 4 w.

.o 1 '/

SURVEILLANCE REQUIREMENTS g#y[g ty, Gsvg e

~

j y,

,y 4.1.11

~~

ach of the above required jet pumps shall be demonstrated OPERABLE o

a N prior t THERMAL POWER exceeding 25% of RATED THERMAL POWER and at least once

• } -] }

per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by determining recirculation loop flow, total core flow and

,g, diffuser-to-lower plenum differential pressure for each jet pump and verifying h le e that. no two of the following conditions occur whqn the recirculation pumps are j vf tyg $)

operating at the same speed.

T va I

() 5 y-[D

!a.

The indicated recirculationkep[ flow differs by more than 10% from 1

ho 3

y, the establishedypump speed-ogtlWeharacteristics.

]

E b.

The indicated total core flow differs by more than 10% from the

/jI 4j'd9 s

established total core flow _value_detived_ fro'shrJErculat1on1Wep v

e 1) flowJeasUramenGN MGQ < ~~rhk WERO q

• b-a t e.Mj*

[q The indicatMiffus_er_-to. lower _ planum _dffierentiiLpressur/g d

c.

of any

.]

individual jet pump differs from the established patterns by more V

f than 10%.- m

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GE-STS (BWR/4) 3/44-f

REACTOR COOLANT SYSTEM 6

RECIRCULATION PUMPS LIMITING CONDITION FOR OPERATION

}

i

/

3.@> Recirculation pump speed shall-be maintained within:

g M

N

/f. t0% of each other withMire fik greater than or equal to 734 of p,crafedicore-~fRWr.+ \\(_QQ~K(g g

A. p~.

ijj{k@of each other with Yore fTod[less than (

9

/..

of 'sted core flok I

i APPLICABILITY: OPERATIONAL GNDITIONS 1*s-y,,, G D & D

.soun and f

7g i

ACTION:

^

With the recirculation pump speeds different by more than the specified limits, either:

/. y Restore the recirculation pump speeds to within the specified limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or

/..

/

. 2.g. (Declare the pacirculatloniloop_ot_the_ pump xith the slower speedSt l

in operation and take the ACTION required by SpecifliatTon%471 TW

('s& T ] [* M Z, j

.~._~

l SURVEILLANCE REQUIREMENTS N

/-

4.4T.1 Recirculation' pump speed,shall be verified to be within the limits at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,

~ -

3 v, s.e speciai 1est exc.ption 2 10.4. -

y

.)

GE-STS (BWR/4) 3/4 4-Y t

4

{l REACTOR COOLANT SYSTEM t

IDLE RECIRCULATION LOOP STARTUP LIMITING CONDITION FOR OPERATION h

w 3'.(1733 An idle recirculation loop shall not be started unless the temperature differential between the reactor pressure vessel steam s ace. coolant and the bottom head drain line coolant is less than or equal to 100 *,, nd:

fg.g ed O

/. V.

When both loops have been idle, unless the temperature differential between the reactor coolant within the idle loop to be started up a and the coolant in the reactor pressure vessel is less than or equal i

2, K.

When only one loop has been idle, unless the temperature differential between the reactor coolant withinQheVdle and operating recircula-tion loops is less than or equal to,(50)'F and the itJ 1.o_oy' cfleirvateis less than or~ equal ~to-(50)%~of ~ rate oop flo_n

w. 7-.

j

[

-m Sh *N

,pecc(s)

[

f" fad 0 AP?LICA81LITY: OPERATIONAL CONDIT!tWS-1, 2,' 3 and 4.

p sg.

ACTION:

With temperature differences and/or flow rates exceeding the above limits, suspend startup of any idle recirculation loop.

i SURVEILLANCEREQUIRel7pS N7 4.43b c-The temperature differentials and flow rate shall be determined to be i

within the limits within 15 minutes prior to startup of an idle recirculation loop.

c.

-n

,, - n ~ - n

~,. ~

-C fb ag pg.udu f'a uu m *Le h f

< < }'u d d s f

-,y 3/4 4-4'4 GE-STS (BWR/4)

f REACTOR COOLANT SYSTEM

. 017E0: 01W AFETY/iiEUE5 LVES SAFETY 7#EUEF'V$[VES

~

LIMITING CONDITION FOR OPERATION bh l

3.f.M ((At le_ast...(two)(afleast'reactorcoolantsystes_ code _safetyvalv safety val ~e" functio!

inf_the_followinglgeactor coolant systemsafety/MIR)Utf v

i valves 4hal e OPERA 8LE with the specified code safety )

h*.!"W L

f 2)'safetyvilves_t_(1146)Tpsf~ti%

b 7,y 1(3)j safity-relief valvesWT ps g 11%

i f%

z

.(3)' safety @ fem if valves 0 (1185 psig 11%

2 fp 3) safety e Haf, valves e (1195) psig 21%

fzg i

safetg relfif> valves e {1205{ psig 11% ).

_c,,

&<A i 4NM,.,y ~ - &

APPLICABILITY: OPERATIONAL GONBITIONS 1, 2 and 3.

skct6 &y &_ c/WN3LL%

. nec m r

ps,J.n w %

d wdw_j~~~'

ACTION:

~

d

/ (.

Withdone or more of'the_above re uired E actor _ coolant _ system _co'datsaf_e b (Vahes_ar_ wi_th),the safety valve unction of one or more of the above l

rsquired safetMfaialves inoperable, be in at least HDT SHUTDOWN 1

within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

g j

b. ~ With one or more (code safety valves or) safety / relief valves stuck open, provided that suppression pool average water temperature is less than (95)*F, close the stuck cpen (code safety valves and/or) safety relief valve (s);

if unable to close the stuck open valve (s) within 2 minutes or if sup-N pression pool average water temperature is (95)'F or greater, place the N reactor mode switch in the_ Shutdown position.

'c T With one or more safety / relief valve (tail pipe pressure switches)

(acoustic monitors) inoperable, restore the inoperable (switch (es))

(monitor (s)) to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within thes following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

'~

./"on-~~m~b m-n-

/

, ~~

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&Ldgduus&% Qf^ggl^'f["; hh","h Eg"a7 2

m.,Cic : 2"';'w. ~v~~

" 4'n.;. '~

'v w

C-L N "The lift setting pressure shall correspond to ambient conditions of the valves at nm.inal ograting temperatures and pressures.

q'

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h h

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4

. - ~ _. _ _ - -

3 (4.4.2.1.1 (The code safety valve function of each of the above required safetyf relief valves shall be demonstrated OPERABLE by verifying that the bellows on the safety / relief valves have integrity, by instrumentation indication, at leastj ce per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.)

J

~

4.4719 Theltal13fpe pressure switch) (acoustic monitor? for each safety [

bulM

.411&f"TialWshall~be demonstrated'0PERABLE with_the_setpoinY veHYled to_b'e%'

h

s((20)_EC5Epifg)'by performance of a:

~

CHANNEL ((FUNCTilNALIESU[(bHEC least once per 31 days, and a a.

CHANNELCALIBRATIONatleastonceper18monthh.

b.

("The provisions of Specification 4.0.4 ar's not applicable pro the Surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressurep adequate to perform the test.)

j q f,$,

W,' 0f['N 4.LZ~ cat least 1/2 of the safetyt@ef valves shall be removed, set pressure tested and reinstalled or repleced with spares-that have been previously set

. pressure tested and stored in accordance with manufacturer's recommendatiorE[h,

t C.at~1 east-~5 Hie pergeonths,and:thiy%hsil be rotated such that allTsafety rFilef' valves are removed, se ressure tested and reinstalled or replaced with spares that have been previousi t pressure tested and stored in accordance with manufacturer's recommendatio stested at~liist once per 40 morttTf. h u m

m s aw a a s a,4 sly-d GE-STS (BWR/4) 3/44-/

M

FE TFM0s ORY c

REACTOR COOLANT SYSTEM j

rW V

O RELIEF VALVES / LOW-LOW SET FUNCTIONj

/

um u

g

(

5.qg,M e 9

LIMITING CONDITION FOR OPERATION t.m y

T23 )The reTref~ Valve fon~:115Eand the low low _ set _ function of the_followTng>

p 4

3.

deactorcoolant_ system safety / relief vaTves shall be OPERABLE with the following settings:

Set Function Relief Fun ion

1. %^w f

Setpoint* (psio) t Setpint psic)O f,4 A th /

alve No.

Open Close]

Ogg (Close \\

AaLe J,a1 k I

a-vw/ 4 AF.

(1033)

(926)

• /'@V

{

B*MA/

(1073)

(936)

J m c<>.;v

\\

(1113)

(946) e v6 %

i

(

(1113)

(946) e me,A T

(1113)

(946) e ve,# M n

)

q

,f-[g APPLICABILITY: OPERATIONAL,GON H T M N6-1, 2 and 3.

+ m s) 4 b

f l

(~GL GTC' l

2.y.

With the relief valve function and/or the toiBoiicrat_tunctic of one of b r<t the above required reactor coolant. system (saf897N11ef valves inoperable, h (d@ s%y j restore the inoperable relief valve function and low-low sot func* ion

'l to OPERABLE status within 14 days or be in at least HOT SHUTCOWN within

[4.g

{

the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within'the_ fo}mTk.dsm1owing_

q Gt2L3 With the relief valve function and/or the 6ow(-losset fGHEtirn of more jp J g.

a ad than one of the above required reactor coolant system 6tely relief _ valves MJ inoperable, be in at least HOT SHUTDOWN within :12 hours and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

RVEILLANCE REQUIREMENTS d

D,% f 4.(.O G h e-

%~

s 2.2.1) The relief valve function and the 4_ow_-low set function preifure sC actuatioiU instrumentation shall be demonstrated _0fEWEBLE'by performance of a:

s 4WL Q L,,M ae %Q p' M )Aj-XiD t

a.

CHANNEL FUNCTIONAL TEST (_fricisding_ calibration 7f'thi'~ trip untti at least onceper$ydays.

M.3 e f y' b.

CHANNEL CALIBRATION, LOGIC SYSTEM FUNCTIONAL TEST and simulated automatic

.h j operation of the entire system at least once per 18 months.

Utg

+

o 9

~

,b Dil

'$ (' y fhda":

6*M3 der

'i e df tid

) (Tne itft setting pressure shall correspond to ambient condi 3

pe,M valves at nominal operating temperatures and pressures.

7 j

mV' 3/4 49/ 1 GE-STS (BWR/4 L 6 sg L.!au a &w 4d L LM "" % &f.

-~

..-m ea9.a + vy,s.

i REACTOR COOLANT SYSTEM ji F

3,4 J.

DEAC'01 COCLANT SYSTEM LEAKAGE LE AGOE :E E:~*0N SYSTEMS LIM-~~4G ::E:~ ION FOR OPERATION t&

3.2.3.1 ine rollowing reactor coolant system leakage detection systems sna11

+T be OPERABLE:

y

/. g.

The prima hontainment atmosphere rticulate s

radioactiv nitar.ane system,

_d i hy J, J L L6 +;O q. g.

The [timary cc 'Masp Uow monitoringhs.tes [ [

fl c.

Either the (primary containment air coolers condensate flow rate

)

monitoring system) or th3 primary containment atmosphere (gaseous o s

particulate) radioactivity monitoring system APPLICABILITY: OPERATIONAL-G g {G 1, 2 and 3.

,}

ACTION:

g ith only two of the above requiret! leakage # etection systems OPERABLE, d

. }i "

operation may continue for up to 30 days provided grab samples of the contain-9 ment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the

. j} j j M required gaseous and/or particulate radioactive monitoring system is

(

M otherwise,- be 'in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD HUTDOWN within the followino 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

s f

N SURVEILLANCE REQUIREMENTS

(

The react

\\gl a,

oemonstrated 0,E Aor coolant system. leakage detection systems.shall be LE by:

k ff

- (f.'f.71Disi.-sis atmosphere particulate and gaseous monitoring

]g } Q

.y j

tystou performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a j

LMANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL i

1 CA'.IBRATION at least once per 18 months.

o.

T-ieary containment sump flow monitoring system performance of a e

n N

CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL l:

CAL:BRATION TEST at least once per 18 months.

i Primary cont,sineent air coolers condensate flow rate monitoring

. ]

system performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.

j

/% 4d*4dsA g p-.- ifc.a.

t.

I z.f p % &eu.uuwvw p L=Kkpa.H M

. cu.

Q k *f && ~ fa 6 m 3

GE-STS (BWR/4) 3/4 4-8 #

= -

~

s h 4h h h

REACTOR COOLANT SYSTEM i

OPERATIONAL LEAKAGE j

1ITING CONDITION FOR OPERATION 3.' M Reactor coolant system leakage shall be limited to:

4 y.

No PRESSURE BOUNDARY LEAKAGE.

3. p.

5 spa UNIDENTIFIED LEAKAGE..

su m.%a-I t, A. 625 gpa total leakage averaged over any 24-hour period.

d.

1 gps leakage at a reactor coolant systes pressure of (5507'I psig from any reactor coolant system pressure isolation valve specif

- - f r. Tattle _ 3.4 L 2-L perio f V. [62 gps increase in UgNEgIFIEDLEAKAGEwithinany -ho

• j[D $((1, APPLICA8ILITY: OPERATIONAL 60NDfT!ONS-1, 2 and 3.

ACTION:

/. g With any PRESSURE B002ARY LEAKAGE, be in at least HOT SHUTDOWN within j

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and ifLCol.D_RELTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4 g6uiosurina4 trMAV.c. 4.td led.g r.tu.

y j

f g.

Withgreactor coolant systes ea a r than the411mits @]Lrd-ana/are ango, reduce the leakage rate within the limits within p4 hours or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTD0let within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

]'

{c.

With av reactor coolant systes pressure isolation valve leakage greater 7 than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least two other closed (manual or deactivated automatic) (or check") valves, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

d.

With one or more of the high/ low pressure interface valve leakage pressure monitors shown in Table 3.4.3.2-1 inoperable, restore the inopernble monitor (s) to_0PERABLE status within 7 days or verify the pressure to be less than the alam setpoint at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />;

[

restore the inr9erable monitor (s) to OPERABLE status within 30 days A

or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD 4

1

_ SHUID0ldLdthin the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

7

_3 Witha[

ant systen UNmgm trar. AGE increas great r

=

than Z gpa within anyT-hour per1on21oentify the source of 1eakage

~

1 p dp increase asJotiervice sens1tive Type 3M or 316 austenitic stainless 7

.iuna e nours or be in at least ET 5HUTDOWN within the next g

p and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.)-

f F*

e m

(Which have been vernies not to exceed the allowable leakage limit at the las e

refueling outage or the after last time the valve was disturbed, whichever f

is more recent.)

p GE-STS (BWR/4) 3/4'4-I#

5

.1* [* @ 8M?t9 * * $M'_#f*98l19R 4 8 , *Y If '[ Yf f f ? 4

• • • '9

'# W

• '*8 r*t

'a j

REACTOR COOLANT SYSTEN d

SURVEILLANCE REQUIRENENTS

4...

The reactor '

ant system leakage shall be demonstrated to be with n each of the sits by:

/, )7 In #the primary containment atmospheric r11cu and e-<Ian==assradioactivity at least once per hour m

s

7. X (HonitorTM6the orina contai nt fMt least once per g a) (12) wen. (a

_44

~

Monitoring the primary containment air coolers condensate flow rate or the (gaseous) (particulate) radioactivity at least once per (4) (12) hours, and d.

Monitoring the reactor vessel head flange leak detection system at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4.4.3.2.2 Each reactor coolant system %ssure isolation valve specified in Table 3.4.3.2-1 shall be demonstrated OPERABLE by leak testing pursuant to

,p Specification 4.0.5 and verifying the leakage of each valve to be within the specified limit:

a.

At least once per 18 months, and.

Prior to returning the valve to service following maintenance, b.

repair or replacement work on the valve which could affect its leakage rate.

The previsions of Specification 4.0.4 are nut applicable for entry into OPERATIONAL CONDITION 3.

44.4.3.2.3 The high/ low pressure interface valve leakage pressure monitors shall be demonstrated OPERABLE with alarm setpoints per Table 3.4.3.2-2 d-by performance of a:-

a.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and b.

CHANNEL CALIBRATION at least once per 18 months.7 p

N l

1 (a)$derL p ' f yo y

- a n

I &

GE-STS(BWR/4) 3/44-g N

L.

d'E wO M'uf5N.D f '9 MiD N'I M ' ' ' 'T * '

'_EY, I_I f_',Y_I [M ? I[ t' 'NY I**'"3*

f* * -

E L -

8 FaINK11M10h DNLY

'j :;

i.. *, M..M TABLE 3.4.3.2-1 REACTOR COOLANT SYSTEP. PRE 55L*RE ISOLATION 'l LYES I

'!ALVE !!L'"EER jYSTEM v

3 t

. TABLE 1.4.3.,2-2 RESCTOR CC LANT YSTEM INTERFACE VAL'!ES

/

1 LEAKAGE PRESSURE MONITORS 1

ALARM SETPOINT VALVE NUMBER SYSTEM (psic) i j

D I

t TV

. GE-STS (BWR/4):

3/44-I Y

J

REACTOR COOLANT SYSTEM f

4N4dHEMISTRY LIMITING CONDITION FOR OPERATION b3D The chemistry of the reactor coolant system shall be maintained within the limits specified in Table 1374 F1; i

APPLICABILITY:

mes

/ p ACTION:

Adr

/g In OPERATIONAL-GONDITION 1: G With the conductivity,hhloride concentration oI;,_pH gxceeding the

% Y.

limit specified in Tablih3TErfor less tharie7z hours during one continuous time interval gd, for conductijyity and chloride concen-tration for less than'D6 hours per year, ttistiivith the conductivity tha4Y.kl0 paho/cm at 25'C and with the chloride concentrat less 'il B ppa, this need not be reported to the Commission'and them (provisions ~of Specification-3:0:4 are not-~EfpHeablef

.bI With the conductivity,fg 1 ride concentration or pH exceeding the limit specified in Tab e J 1'for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during one continuous time interval or with the conductivity a chloride - @ ~D concentration exceeding the limit specified in Tabi C4 W for more than 336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br /> per year, be in at least STARTUP w in the next (O 7 f hours.

4'.

With the conductivity exceeding 10 paho/cm at 25'C or chloride concentration exceeding 0.5 ppa, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2. y.

In OPERATIONAL CONibhN-2 and 3 with the conductivity, chloride.M concentration or pH exceeding the limit specified in TableTC4D for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval, be in at least HOT SHUTDmdN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the

( c io11owing.24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3X.

At all other times:' % _

LJ.

With the:

kl-4)n L <a)

ConductivityorpHexceedingthelimitspecifiedinTable3M'Fl(

restore the conductivity and pH to within the limit within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or v

Chloride concentration exceeding the limit specified in Table M(ti) A 3 M D frestore the chloride concentration to within th 2

i U"-

within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the reactor coolant system. Determine that the structural integrity of the reactor coolant system remains acceptable for continued operation

' prior to proceeding to OPERATIONAL 41Hjp!,TJON'3.

I

);' The provisions of Specification 3.0.0 are-not applicable.

q i

GE-STS (BWR/4) 3/4 4-V ff s h

t moA

• v & a p. hp m - q a.S:m n no n s

eno x --n,- nn c

m J l i

REACTOR COOLANT' SYSTEM Ih L

I

\\

SURVEILLANCE" REQUIREMENTS l

-1

_j 4.

, The reactor coolant shall be determined, to be within the specified chem stry limit by:

/, g Measurement prior to pressurizing the reactor during each startup, if not performed within the previous 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

I 1

2, g.

Analyzing a sample of the reactor coolant for:

a%

Chlorides at least once per:

/. (af 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and 2-4t) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> whenever conductivity is greater than the limit in Table @ 347 Q g i b < J' Condudivity at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

c g.

pH at least once per:

a 72'hciG~rs, an b) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> whenever conductivity is greater than the limit-

' in Table % 4 %

g y, g Continuously recording the conductivity of the reactor coolant, or when the continuous recording conductivity monitor is inoperableg, v

<1Tu-31Dsr obtaining an in-line conductivity measurement at least once per:

No DC (5) a %.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> in OPERATIONAL-20NDITIONS 1, 2 and 3. and' b g.

-24 hours at all other times.

t/, %

Performance of a-CHANNEL CHECK of tho' continuous conductivity-

~

monitor with an in-line flow call at-least once per:

2 l'.

7 days, and b - )'.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> wheaever conductivity'is greater than the limit in' in Table G K 't.

i Wm 1

i GE-STS (BWR/4) 3/44-pf" y,

'w!

M TABLE. 4-1; e~

9 REACTOR COOLANT SYSTEM g

CHEMISTRY LIMiiS

/nes a s)

OPERATIONAL C0letYtelt-CHLORIDES ColeUCTIVITY (pahos/cm 925'C)'

,gt y

=>

1-1 0.2 ppe i 1.0 5.6 i pH i 8.6

=*ril 2 and 3 1 0.1 ppe i 2.0 5.61 pil 18.6 CC3 W

At all other times

_ i 0.5 ppe i 10 3 5.3 $ pH $ 8.6 G

' %:3m

---4 m

O N'

3 r--

e m.

.____________m. _ ___.____.____ _,_ _ _._

1

~

p-2 F01WMATE UU REACTOR COOLANT SYSTEM

-3/4f5[SPECIFICACTIVITY Cf,T MITING CONDITION FOR OPERATION vs

$e specific activity of thehprY$$'[h> coolant shall be limited to:*

A

("i.f Less than or equal to 0.2 microcuries per gram DOSE EQUIVALENT I-131, jnd(

h Less thanA equal to 1004 microcuries__per grkW APPLICABILITY: OPERATIONALCg 1,2,3TanL4 M "

ACTION:

m x fs)

/.,a'.

In OPERATIONAL 69NHTIONS-1, 2 or 3 with the specific activity of the p plant F

[

Greater than 0.2 microcuries per gram DOSE EQUIVALENT I-131 but

~

less than or equal to 4.0 microcuriesJer_graaf operation may '

JcIntinuai~f6r UpV48' hours ~pr:Hii~di~d that the cumulative operating time under these circumstances does not exceed 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in any l

consecutive 12-month period. With the total cumulative operating time at a primary coolant specific activity greater than 0.2 micro-curies per gram DOSE EQUIVALENT I-131. exceeding 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> in any consecutive six-month period, prepare and submit a'Special Report to the Commission pursuant to Specification 6.9.2 within 30 days indicating the number of hours of operation above this limit. The provisions of Specificatio ILA.are not applicaJb 2.

GreaterJhan 0.2 microcuries per_ gras' DOSE EQUIVALENT 'I-131 for more than 48'hou'7s'durihg one continuous time iritarvaV6r T6g

~

'more than 800~h60yF7Ulstive operating-timiiTn a:consecuitiva.

~-

-l N

12-month Criods or greater than 4.0 microcuries per gram be in at least HDT SHUTDOWN with the main steam line isolatio valves

@Mu closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

pi 3.

Greater than 1004 microcuries per gram, be in at least HOTN SHUTDOWN with the main steamline isolation valves closed within -

'E$/

_pj$,. }-

n b.

In OPERATIONAL CONDITIONS 1,' 2, 3 6 with the specific activity _

i ref~th~eyrima~ryiciiolent greater than D microcuries per gram DOSE i

,; Q EQUIVALENT ~F131(stgreaWthan1anA sterneuries_ner_gramTperform the sampling and analysisaguiremen. ofgItem 4Cof Table 4.'CEQ'cD until the specific activityif tf

~ 9 coolant is restored to within its limit.fA-tEp0RTA8tf MukkeiiCE shEl be prepared and.

(Tu~ sitted't3~~the Commission pursuant to Specification 6.9.1.

This

/

b report shall contain the results of the specific activity analyses

' t.

and the time duration when the specific activity of the coolant g

exceeded 0.'2 microcuries per gram DOSE EQUIVALENT I-131 together with l

Qfo11owing additional information.

/7 GE-STS (BWR/4) 3/4 4->5 Y

F0mF0MED:OLY REACTOR COOLANT SYSTEM l

' LIMITING CONDITION FOR OPERATION (Continued)

~

ACTION (Continued) 3 A.

In OPERATIONAL CONDIT40N 1 or 2, with:b% of RATED QL THERMAL POWER chgoged by more tha in one hou F, or -

G L A q@

k (.

The off gas leve 4td8C57&E',increasedbymorethan microcuries per second in one hour during steady state ope ion j

The off gas level,Tt31iE5]AE8n$gpocu, ries per s at release rates less than(7$','000 p"d{p 1.

creasedbymorethan((15)%in

'i one hour during steady state operation at release rates greater

@__~ _

thanRS 000Painocuries per second, q(g)-

- perfors M-($~Tablec41,the sampling and analysis requirements o d to within its LimitJPrepare and tubmit ts~tWe7 1'

-Commissibfi a Special Iiipo_rt pursuant to Specification 6.9.2 at'

~

least once per 92 days containing the results of the specific activity analysis together with the below additional information,

j or each occurrence.

7 dditional Information 1.

Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to:

a)

Thefirstsampleinwhichthelimitwasexceeded,and/or\\

b)

The THERMAL POWER or off gas level change.

2.

Fuel burnup by core region.

3.

Clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to:

a)

The first sample in which the limit'was exceeded, and/or b)

The THERMAL POWER or off gas level change.

4.

Off-gas level starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to:

a)

The,first sample in which the limit was exceeded, and/or W ho THERMAL POWER or off gas level change.

.I SURVEILLANCE REQUIDEMENTS

[1 4.@,The specific activity of the reactor coolant shall be demonstrated to be within the limits by performance of the sampling and analysis program of Table (![FJ4

{g

}

bt appiiAe during the startup test prograDn q

GE-STS (BWR/4) 3/44f/7

.:l TABLE 4.4.5-1 g

J.

PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAN Ct

,n cGG)

OPERAT10NAl-CONDtitONS-n TYPE OF MEASUREMENT SAMPLE AND ANALYSIS IN MIICH SAMPLE AND ANALYSIS FREQUENCY AND ANALYSIS REQUIRED

1. ^

Gross Beta and r-Activity At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 1, 2, 3 Determination m

CD 2.

Isotopic Analysis for DOSE At least once per 31 days 1

EQUIVALENT I-131 Concentration adlochemical for E Determination At least once per 6 months

• 3, /.

Isotopic Analysis for Iodine a) At. least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

C 2b whenever the specific E

activity exceeds a Ilmit w

as required by ACTION g M d'

C::3.

y, b) At least one sample, between 1, 2 llEE!

g 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following the g

change in THERMAL POWER or g

off gas level, as required by ACTIONtc { J ],

=-ec 4/.

Isotopic Analysis of an Off-.

At least once per 31 days 1

gas Sample including Quantitative Measurements for at least Xe-133 Xe-135 and Kr-88

5 ample to be taken after a minimum of 2 EFPO and 20 days of POWER OPERATION have elapsed since reactor w a# s W ritieel-for 48_houts_mc_ longer r

_sp,c70ntl1 the specific activity of the pe4eary coolant system is restored to within its ilmits.

mW l

~

l

-.-.._._._,._.-____..._.__-.__m._.mm._

m w.

w

.-ew.

v-.m.

4 5

REACTOR COOLANT SYSTEM 3/454.6bRES$URE/TEMPERATURELIMITS REACTOR-COOLANT SYSTEM LIMITING CONDITION FOR OPERATION S Y The reactor coolant system temperature an shall be limited-accordance with the limit lines shown on Figure 3/4~lEll) curve (A e5d*

1 for hydrostatic or leak testing; (2) curvei 8 and~R'J'for heatup by non-nuclear means, cooldown fo11owing a nuclear shutdown and low power PHYSICS TESTS; and

~

(3) curve (C 'anECFfor operations with a critical core other than low power PHYSICS TESTS, with:

+ r

/g.

A maximum heatup_of ((100)*F in ~any one hour period,

%~Mi.i (K.

A maximum cooldown of ((100)*F in any one hour period, 3. s'.

A maxim e change of less than or equal to 20*F in any one hour period during inservice hydrostatic and leak testing opera-tions above the heatup and cooldown' limit curves, and 2d Y. M The reacto vessel flange and head flange temperature greater than or equal to ((70_)*F when reactor vessel head bolting studs' are under tension.

APPLICABILITY: At all times.

ACTION:

With any of the above limits exceeded, restore the temperature and/or pressure to within the limits within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the reactor coolant system; determine that the reactor coolant system remains acceptable for continued operations or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS W1 4.4'fu1Ji During system heatup, cooldown and inservice leak and hydrostatic testing operations, the reactor coolant system temperature and pressure shall be determined to be within the above required heatup and cooldown limits and to N(CK f as applicable, at least once per 3 ' minutes.

the ri ht of the limit lines of Figure 3.4'5~EFiEurves A-JA'~~B'And BTo34 h

gp m 2

~.

GE-STS (BWR/4) 3/4 4-y g

X N

S i-4

FOR 1F05AT10:1 OhLY REACTOR COOLANT SYSTEM.

' SURVEILLANCE REQUIREMENTS (Continued)

~

.(b.

The reactor coolant system temperature at the following location shall be determined at least once per 5 minutes until 3 successive temperatures at each location are within 5'F:

1.

Reactor vessel bottom drain, 2.

RecirculationloopsdandB,and

• • ?N

$Y'!

1 g

IY,?

4.4 20The reactor coolant system temperature and pressure shall be determined to beJo the right of the criticality limit line of Figure 3%fLl-1 curvesC (ariCCYwithin 15 minutes prior to the withdrawal of control rods to bring the reactor to criticality and at least once per 30 minutes during system heatup.

.g, 4.'4JL13) The reactor vessel material surveillance specimens shall be removed and examined, to determine changes in reactor pressure-vessel material as required _by%ults~of~these examinations shall properties,4.671T3-1.

in~Tib1T4.

The (the._curvesofFicure3.4.6.1-1.;

!'he reactor vessel flange and head flange tem 4 E4 C

verified to be greater than or equal tejQD{:g) perature shall be-T a.

In OPERATIONAL 4818 tit 0K 4 when reactor coolant system temperature.

is:

y>*F, at.least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

1.

100 2.

3,[80)*F,atleastonceper30 minutes.

b.

Within 30 minutes prior to and at least once per 30 minutes during tensioning of the reactor vessel head bolting studs.

1 E 4-

GE-STS (BWR/4) 3/44-[

EmFMull010U

%/

Ny s g (7 Nd h,A C-sf'C h

4,(J,/

t,4A &

A e

j

_REAk8' fr [

l

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t..=.,ss,

=

i

'i' 8

. : Nom.MLTWNE;: --...

- l M=8'8. ---...

l "-

==

UANT U

5 l

C-::::

Efs-g

, =.. --

"---~. M j jM" A = NETIAL3Y5TRA MYDnD i:

' :=s :

TEsf unNT i

=r:

3E COM SELTUNE.,J

..:ag a 8 = INITIALNON=WUCLEAR jij J

8 EATING WEET

?

.a.. A.FT._ERENI.P.T. m n=::

~ '

.8!

C - BitTIALNUC& EAR CChi E:

1:

~ 2":~

M j

: :::.:.] \\'

g :=g CRt11 CAL WEET SABED g

4

. CBS 6.E. Buta UCIBISING z=::

Ns, :'=_;1 TOPICAL REP 4 NIT NEDO.

g

. 4-J 4--

m:,

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2f775 E"

......._..]'

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_ca f

._,t-r Puces AN iftfTlAI.

3 1

RT OF WP-

~

ca, n. : :.:s...,

seer

..,.....g 3 f..

=::t we

...: f :. ffI r...

e, s.

888 2

..g-a ~._g e t.;....

9-,,;y pg

,,.,o

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4..

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E

[.

". ~ ' " 1-PREDuuATER NOZELA...

~

~

,,,a.

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==

a

-~

2 :

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T.

i.~

i T>as Pieuna Pon u.LusTnATian anty

'.. "..,. i.i.i.i ao Noruns Pon openAinaN j

= soLTup.

:

s LN.uf.

. =..

Curve (s) ( ) applicable for

_iiEi

~

g.---

service periods up to (

) EFPY iis.

ano i

(and contain margins of (10)'F

.X = = and (60) psig for possible-

~.

.="

.- _ /,........=. _ instrument errors).

-=

.. =....

-.=

,d,,

- -s

=-

o too me zoo ao see (RPV Metal) Temperature (*F)

MINIMUM (REACTOR PRESSURE VESSEL METAL) TEMPWTURE VS. REACTOR VESSEL PRESSURE

,..s:

Figure 3.4.6.1=1 s

i GE-STS (8WR/4) 3/4 4-

ri?

FOR 1F0E1ED: JJLY p

US Eb a-

=

i 3R E

\\a w

a

']

e 5

5 r,

g 1

w e,

er d

w

\\

t R

E*

a5

)

f W:

06 a

M

>S w

S

\\

GE-STS (BWR/4) 3/4 4.21

-l

E E

.0; 0;W R8.tCT_0R COOLANT SYSTEM

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' REACTOR STEAM DOME TJ LIMITING CONDITION FOR OPERATION u

N.'."(~5E F.~ The pressure in the reactor steam done shall be less than

-1045))' psi g.

3 OPERATIONALCONDITION1{and2.'Ti b, _

G APPLICABILITY:

g% og h r:7 i

ACTION:

With the reactor _ steam done pressure exceeding 1 04$17sig, reduce the pressure to less than*{l04 n at least HOT SHUTDOWN

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within12 hours.%)3psigwithin15minutesorbe T

kasf)

SURVEILLANCE REQUIREMENTS

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@34.LT2L,The reactor steam done pressure shall be verii'ied to'be less than 104SDp'sig at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

j ne m,-LL39 ot applicable during anticipated transients.

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- GE-STS (BWR/4)'

3/4 4; 22 '

j-e

l, Fa UFORVALD101Y REACTOR COOLANT SYSTEM CIINAIN STEAM LINE ISOLATJON VALVES 1

LIMITING CONDITION FOR OPERATION

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3.17[Two main steam line isolation va]ves (MSIVs) per main steam line shall be OPERABLE with closing times greater than or equal to d3) and less than or equaltoK5), seconds.

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.m oui APPLICABILITY: OPERATIONAL {0NDITTifMF 1, 2 and 3.

ACTION:

(af With one or more MSIVs inoperable:

l L [ Maintain at leart one MSIV OPERABLE in each affected main steam line that is open and within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, either:

l

/, ta[ Restore the inoperable valve (s) to OPERABLE status, or z @f Isolate the affected main steam line by use of a deactivated

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MSIV in the closed posi, tion.

A d.)

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> sad in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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ivisions of Specification 3.0.4 are not applicablha f

SURVEILLANCE REQUIREMENTS WIYr 4f4J' Each of the above required MSIVs shall t,e demonstrated OPERABLE by verifyingfullclosurebetween((3)and(5}secondswhentestedpursuantto Specification 4.0.$.4

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6 GE-STS(BWR/4) 3/4 4- #

FnIMO M 0101Y

~ REACTOR COOLANT SYSTEM h34?C8 STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION i

d 8 The structural integrity of ASME dode Class 1, 2 and 3 components'shall be maintained in accordance with Specification 4.1Qr<g

mow, APPLICABILITY:

OPERATIONAL GGI'ZCitS 1, 2, 3, 4 and 5.

.j ACTION:

/%

With the structural integrity of any ASME Code Class 1 component (s) not conforming to the above requirements, restore the structurai integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature more than 50*F above the minimum temperature required by NDT considerations.

2[.

With t.he structural integrity of any ASME Code Class 2 component (s) not conforming to the above requirements, restore the structural int 9grity of the affected corponent(s) to within its limit or isolate the affected component 15))prio Ftd increasing 'the Reactor _Coolan d (SfsTain'temperaturrabove 200'F.f

3. ):'.

With the structural integrity of any ASME Code Class 3 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its' limit or isolate the affected component (s) from service.

The provi31ons_nf._ Specification _3,1.4 are not'applicabDyb SURVEILLANCE REQUIREMENTS j

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4.f8) No requirements other than Specification 4.045.

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GE-STS (BWR/4) 3/4 4-2(

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REACTOR COOLANT SYSTEM gYMffDUAL uSALRENbd HOT SHUT 00WN LIMITING CONDITION FOR OPERATION D [ Two tdown cooling loops Cthe residual heat._removaLLdfR)r'"-

A -tsystem1shall be OPERABLE and, unless at least one recirculation pump isA n operation, at least one shutdowr. cooling WosW loop shall be in operation 'wp g

with each loop consisting of at least:

'fLA

/g One OPERABLE *RNR pump, and

).

OneOPERABLEhB$eatexchanger.

hy awe APPLICABILITY: OPERATIONAL CONDITION-3, with reactor vessel s

less than the AHR. cut-in permissive setpoint.

ACTION:

g With less than the above required (tion to return the required loco

/ A'.

immediately initiate corrective ac OPERABLE status as soon as possible. Within one hour and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, demonstrate the operability of at least <>ne GR alternate method capable of decay heat removal for each inoperable 6

/@.

Nhlitdown_ccoling. anM loop. Se in at least COLD SHUTDOWN within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.**

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With no WitR> shutdown cooling mode loopain~ operation, isimedi'ately initiate

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s.

correct've action to return at least one he> to operation as soon as possibla. Within one hour establish reactor coolant circulation by an alternate method and monitor reactor coolan temperature and_ pressure at least once per hour.

g SURVEILLANCE REQUIREMENTS Y

4 1 At least one shutdown lin'gJuid6Yoop '6Li.h'emiduathaaLts aW

system l/( alternate method shall be determined to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

f a k v w $* 4 m q p *9 ~f y nw I

T0ne tRRThutdown cooling mode loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided the other loop is OPERABLE and in operation.

hiis shutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period provided the other loop is OPERABLE.

P n.x Q,"hWThe1tHR shutdown cooling mode loop may be removed from operation during hydrostatic testing.

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Whenever two or more %HR> subsystems are inoperable, if unable to attain COLD SHUTDOWN as required by this ACTION, maintain reactor coolant temperature as

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' low as practical by use of alternate heat removal methods.

.)

77 GE-STS (BWR/4) 3/4 4,25

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orm REACTOR COOLANT SYSTEM COLD SHUTDOWN LIMITING CONDITION FOR OPERATION Two utdown cooling de ioopscif_the_ residual _ heat.-removald RiiR N1 '

%syst'eW shall be OPERABLE and, unless at-least one recirculation pump is iy@ _

s operation, at least one shutdown cooling'ai6daNop shall be in operation *'

with each-loop consisting of at least:

LY.

One OPERABLE titt pump, and 7GO L 6.

OneOPERA8LL8HRheatexchanger.

APPLICABILITY:

OPERATIONAL-GONDITION 4.

a new ACTION:

h With less than the above required t

cooljng_mo W 1 oops OPERABLE, within one hour and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, demonstrate the operability of at least one alternate method capable of decay heat removal for each ino leRRHR shu own cool n~g~

sip 2. )h[.

With nbHR shutdowDJ:561JEgTm5dF loop /in operation, within one hour establish'riaictor coolant circulation by an alternate method and monitor reactor coo?r' tgrature and pressure at least once per hour.

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SURVEILLANCE REQUIi:EMENTS DN ypc 4.t4f2IAt least one whutdoin_ con 13ng_moddaloop Tof the resida=1 heat reso

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isyifmW or alternate method shall be determined to be in operation and circula ing reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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JtHRr hutdown cooling %Y1oop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for

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surveillance testing provided the other loop is OPERABLE and in operation.

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Q' L 4EIht shutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per. 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period provided the other loop is OPERABLE.

hkNhe shutdown cooling EdeTop say be removed from operation during hydrostatic testing.

e GE-STS (BWR/4) 3/4 4-3(r

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(tupo a77rs CGiAj' REACTOR COOLANT SYSTEM r

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3/4.i@RESIDIML HEAT REMOVAL b

lIOTSHUTDOWN LIMITING CONDITION FOR OPERATION 3 @l Two tdown cool loops of the residual heat removal (RHR) system shall be OPERABLE #and, unless at least one recirculation pump is__i operation, at least one shutdown cooling mode F fshall be lIn operation *'

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with each (fog' consisting of at least:

G~ J,Q D>

4^

,g a.

One OPERA 8LE RHR pump, and c,4 -(

A b.

One OPERABLE RHR heat exchanger.

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mec 3pb APPLICABILITY: OPERATIONAL-GONDITION 3, with reactor vessel pressure less than p,

the RHR-cut-in permissive setpoint.

ACTION:

59 dh

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With less than the above required RHR shutdown cooling no pe OPERABLE,

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immediately initiate corrective action to return the requiredWaps"to N

OPERABLE status as soon as possible. Within one hour and at least once

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per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, demonstrate the operability of at least one -

(4 alternate method capable _of decay heat removal for each inoperable RHR -

M shutdown tooling op p".' Be in at least C0g5" "" within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> g

, dt~ifn, immed[ately initiate t [.

With no IUR shutdown cooling modeb

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i p_e corrective action to return at le to Wagrat. ion (as soon at o/k / '

g 3j possible. Within one hour establi nacto coolant circulation by an d,5 alternate method and monitor reactor coolant temperature and pressure at l

( (JA least once per hour.

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w..,f-M SURVEILLANCE REQUIREMENTS Y###

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4.'41P At least one shutdown cooling mode 4 Esp"of the residual heat removal n

system, r alternate method shall be determined to be in operation and circulating a

,p'i reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,

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- -bedu'nbeb e.____. _wg**wk]

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I' dr$e RHR s5uS5wn51Tng mode loop may be Inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> foPu suevaillance testing _provided the other loop-is OPERA 8LE and in_oparation/

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• The shutdown coonng pump may bTremoved from operation for up E2~ houri L

-g per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period provided,the other loop is OPERA 8LE.

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h%ihe RHR shutdown cooling mode ep Tay be removed from operation during hydrostatic tasting.

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@d'Mhenever two or more RHILsubsystems are inoperable, if unable to attain COLD I

SHUTDOWN as required by this ACTION, maintain reactor coolant temperature as low as practical by use of alternate heat removal methods.

GE-STS (8WR/4) 3/4 4-25' 7 7

& V U CE-77'G3 0

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REACTOR COOLANT SYSTEM COLD SHUTDOWN LIMITING CONDITION FOR OPERATION i

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3.(

.2' Two shutdown cooling mode toopt _ the residual heat removal (RHR)

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, system shall be OPERA 8LE"and, unless at leasQne recirculation pump is in operation, at least one shutdown cooling mode h]8FsDiha11 be d'n

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with each Goo ~/ consisting of at least:

a p ts_~. d

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One OPERABLE RHR pump, and

'ecA d#

1 p[.

One OPERABLE NIR heat exchanger.

Mo oc~

APPLICABILITY: OPERATIWlAL CONDITIOO4.

ACTION:

[

/. p With less than the above required RHR shutdown cooling mode Woj[0PERABLE, within one hour and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, demonstrate the operability of at least one alternate method capable of deca heat cM'M removal for each inoperable RHR own coolino mod

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gwu,x2 Wit c.

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%Q,*[*5 o""f" With no RHR shutdown cooling modei Emparationfid n one hour establish reactor coolant circulation by an alternate method and monitor a.w a t-reactor coolant temperature and pressure at least once per hour.

SURVEILLANCE REQUIREMENis djh 47 M2 4.43.2 At least one shutdown cooling mode 4Toogi of the residual heat removal system or alternate method shall be determined to be in operation and I

circula ing reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

NCSS ifj

1. ne RHR shutdown cooling mode loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for 0

surveillance testing provided the other loop is OPERA 8LE and in operation.

• The shutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period provided the other loop is OPERA 8LE..

MtC

@ffeThe shutdown cooling mode loop may be removed from operation during 4

hydrostatic testing.

GE-STS (BVR/4) 3/4 4-7#

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