ML20099E872

Rev 7 to Surveillance Procedure Sp 1303-1.1, RCS Leak Rate

ML20099E872
Person / Time
Site:	Crane
Issue date:	05/25/1976
From:	GENERAL PUBLIC UTILITIES CORP.
To:
References
SP-1303-1.1, NUDOCS 8411260117
Download: ML20099E872 (26)

Text

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ATTACHMENT F-SURVEILLANCE PROCEDURE i

SP 1303-1.1

" REACTOR COOLANT SYSTEM LEAK RATE",

REVISION 7, MAY 25, 1976 8411260117 760525 PDR ADOCK 05000289 P

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- m W A/ 2 - igrg TMAtt MILE 13 LAND NUCLEAR $*A7!04 UNIT el SURVE!LLANCE PROCEDURE 1303-1.1 AC $YSTEM LEAK RATE Reovired Interval -

0411y, when RCS temperature 5258 F.

c 1.0 M To evaluate reactor ecolant system leakage in accordance with Technical Specification Table 4.1-2 f tem 7.

2.0 PLANT-STATUS 2.1 Reactor coolant system tasperature is greater than 5250F.

2.2 The Make Up Tank level is between 66" and 96".

2.3 The pressuriger level is greater than 200".

2.4 Aeactor power, temperature and pressure are in a steady state condition.

(i.e. initial and final conditions approximately thesame.)

3.0 U MITS AND PRECAUTIONS 3.1 Aveld addition and removal of water from the reactor coolant and Make-Up systans during this test. The following operations should not be conducted during this test:

Make-Up or chemical addition to the mak6-up system.

a.

b.

Sasoling of the RCS or make-up system.

Venting or draining of the RC5 or make-up systen.

c.

d.

Changing purification dominera112ers or make-up filters l

in service, e.

Beration or detKration.

1.0 meAmammee'=

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3*1.I W AY 2 - 19?$

Revtston 4 3.2 The RCS and makeus system should be maintained in a stearty a

state ccedittor during this test. Changes in valve line-ucs, coolers in service pumps-in-service, etc. should be avoided.

3.3 For the most accurate deteenination of the RCS leak rate, the initial and final conditions of reactor Dower. RCS temperature.

[

pressure and pressurizer level should be identical.

3.4 The same sources should be used when recceding initial and h aal RCS temperature, pressurizer level, make-up tank level w

and ACDT level. Differences in sources could be misinterpreted

{

as RC3 leahage'when comparing successive readings.

3.5 Minimize power level variations during this test.

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4.0 LOCAff0N OF SYSTEM / ASSEMBLY NOTE:

see enclosure two for sources of data.

4.1 The emeputer is the favored source of information.

4.2 If two or more inputs are nct obtainable on the computer, the patch panel is to be used to obtain the required data.

5.0 EQUIPMENT 5.1 Eculpment for use on patch panel.

5.1.1 Digital voltmeter tapable of readkg +,10 VOC.

l 5.1.2 Leeds for patch panel to voltseter. -

6.0 Pe0CEDURE 6.1 If the computer is ava11atte. initiate the " Reactor Cooland; Leakage Test" as detailed in Enclosure !!. Data sheets for e

hand calculations are provided for use as follows:

Data sheet Eor Use When i

p:l; 4

1303-1.1.1.1 Computer is operational gg_

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l 1,303-1.1 etay 3 193-Revision a but not avatlebte for RC3 program.

1303-1.1.1.2 Computer not operational 4.2 If a hand calculation is being performed, obtain the applicable data sheets (see steo 6.1) and take the initial set of dat..

After a minimum of one hour, take the final set of data and i

determine the not RCS leak rate as per instructions on the l

data sheet.

l 4.3 If changes to the RC3 inventory must be made during the r.arfor-stats of this test. *.ney must be accounted for using Data Sheet 1103-1.1.3. Operations such as adding water to the Nake Up Tank or sampling the RCS may be accounted for in this manner.

4.4 If the not RCS leakage is excessive as defined by tna acceptar.ce criteria in section 7. proceed as follows:

6.4.1 Perform another determination of the RC3 leak rate.

6.4.2 Insure that no un-accounted for cperator action has occurred that would change the RCS inventory. (!ee section 3.1 for a listing of possibilities). If such an action has occurred. It invalidates ti.e measurement.

Enter this in the " Remarks" section of the data sheet.

clearly describing the action that invalidated the measure-ment.

4.4.3 Initiate action to determine tad source of leakage.

Check items such as:

a.

Proper valve line-up.

3.0

.'=

Ge ",:ca.

". 'a 9 2.

valve stem leakage.

C.

Make-up puft0 paca199 glands.

Relief valves not saated croperly.

4.

6.4.4 If sources of leauage are found, initiate date sheet 1303 1.1.2. -

l a.

Docewnt completely the source of leakage.

(Examole:

Mu-V-159A stem leakage through packfeg gland).

E b.

Determine the leak rate. TL # most perferred method is to collect the leakage in a calibratac container.

Ij I

(Obtain from Chemistry Dept.) over a known period of f,

time. Use data sheet 1303-1.1.2 to document the method used to determine the leak rate. Include:

l Model 8 & Serial # of DVM used description of other equipment used, tength of measurement and quantity h

li of leakage collected (Example: Used 50 cc graduated cylinder to collect 40 cc of water in 10 seconds.)

Determine the leak este and enter on Data Sheet c.

1303-1.1.2.

This quantity may be subtracted from the net RCS leakage (Line 8C of Data Sheet 1303-1.1.1 and 1.1.2).

d.

The Shift Supervisor shall make the initial determi-nation of the safety implications of the leak.

If he decides that there are possible safety implications, he shall notify the proper personnel in accordance with AP 1014.

l 7.0 ACCEPTANCE CR!TERIA.

4.0

3;a-

Reetssce 5 13/?6/75 7.1 If the gross reactor coolant teamage rate (! tem 7 of Cata Sheet; saceeds 10 gem tne resetor shall e, placec in %t shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of detection.

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. cg = g * ; e 7.2 If uniceatt'iec reu tur :os:4nt ledtace **te" S c' Cdt2 5"*et oncetos i gpm Of tne retctor snell De olaceo le not shutdown within 24 8 tours of detection.

7.3 If any reactor coolant leakage is evaluated as uns.te, the reactor small be placed in not shutdown witntn 24 neurs o' detection.

7.4 If any reactor coolant leakage exists througn a non-isolable fault i.i a RCS strength boundary (such as the reactor vessel, piping, valve body, etc., except the steam generator tubes),

the reactor shall be s?.utdown, and cocidown to the cold shutdown condition shall be initiated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of detection.

7.5 If reactor shutdown is required by criteria 7.1, 7.2, 7.3, or 7.4 the rate of shutdown and the conditions of shutdown shall be determined by the safety evaluation for each case and justified in writing as soon thereafter as practicable..

7.6 Action to evaluate the safety implication of reactor coolant leakage shall be initiated within four hours of detection.

The nature, as well as the magnitude, of the leak shall be considered in this evaluation. The safety evaluation shall assure that the exposure of offsite personnel to radiation is within the guidelines of 10 CFR 20.

7.7 If reactor shutdown is required per Specification 7.1, 7.2, 7.3, tre reactor shall not be restarted until the leak is repaired or until the problem is otherwise corrected.

7.8 1.oss of reactor coolant through reactor coolant pumo seals ard system valves to connecting systems which vent to the gas vent header and from which coolant can ce returned tc the reactor

5. 0

- - - - ~ ~

1303 1.;

uar 2 1979 Revis'ce 4 coolant system shall not be consteered as reactor coolant leakage and shall not se sucject to tne conetcerstion of tne aeeva criteria escept that suca losses when added to Ivakage shall nt.t exceed 30 gpe. If leakage plus losses exceeds 30 gem the reactor shall be placed in hot shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of detection, i

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i 12C3-1.1 UAf 2 1975 Rev'v an 4 CATA 5HECT 1303-1.1.1.1

9' I "# 5 For Use 'nen Computer is Ave 114 ele a

Initial Conditions - To be taken at one minute intervals Computer Point T

k1DL,[

Time g

72 73 T.

2 L_ine 2a Tc Lood A 510

,3 Lt d Tg Loop A 504

+

3 Line 2c Tg Loop B 513

+ __

+

,1 Line 2d Tg Loop B

$09

+

+

3 Line 2e Unit Teve (Sus of Lines !a. 2b. 2c and 2d + 4)

_.4 kla. g,,],

Prze Level 1720

+ _

,3 klae4 MU Yg Level 494

+

,3

+

(l.ag,1 RCDT Level Patch Penel DVM

+

+

,3 Final Condttions - To be taken at one minute Intervals Camputer I

M Time 1

2 I3 T*

2 Line 7a Tc Loop A 510

+

+

.3 Line 76 TN Loop A 504

+ _

,3 Line 7e Tc Loop B 513

+

+ _

,3 ki 1,,1fi, Ty Loop i s09

~

+

,3 Line 7e Unit Tave (Sum of Lines 74, 7b, 7c and 7d e 4)

,4 klag,,,f, Przr Level 1720

+

,3 (Lag,,,f, MU Tk Level 494

+

+

,3 Line 10 RCDT Level Patch Panel DVM

+

3 l

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33g3,i,3 r&.'5/te Revtsson 7 Page 2 of 5 Et Carry Algebrate signs throuen all steps.

1.

Most change due to AC3 Temwrature change.

(use Itne to and Figure 1 to detemine riensity)

M a.

Initial Sensity 1bm/ft3 (use Itne 7e and figure 1 to detemine density)

L,13L,11 b.

Final Density lbm/ft3 c.

RCS Volume change (line !! ninus line 12 = 10,673)

Line 11 Nines Lfne !!

Line 13 10.873 ft3a_

IN/ft3*

Ibn 2.

Moss change in Part. Level (Line 3 minus Line 4 a 120.8)

Line 3 inus Line 8 Lfne/ 4 120.8

_ in e_

In chaage in MU fant Level (Lfno 4 minus L!e ! : 2'016:/fc.)

Line 4 Nimes Line 9 i

M 250 n a in

=

1he 4.

Total RCS Mass Change (Algebraic swi of lines 13,14 and 15)

Line 13 Tave chenee of mass Line 14 Pressurizer mass change Line 15 MUT mass enenge Line 16 Ibn 3.0

1103 1.1 oevision 4 peep i of 5 WAY 2

• 1975 5.

Total RCS change in gallons a.

N an fave (line 2 plus line 7;

• 2)

Line te _ 09 Rine 7e OF Line 17

_e ! e _OF b.

Use figuri 2 and Line 17 to find Line 18 conversion factor frem Ibn t sallons:

cal /lba IICS Inventory change (Line 16 times Ifne 18) c.

Line 18 lbs (laf,.19 mLine 18 cal /lbe= J a1 d.

Operator caused changes to system Line 20 (fres data sheet 13031.1.3):

cal e.

Total llCS leakage plus losses (AlgetreicsumofIfnes19and20) t Line li _

Line 20 Line 21 sal.

4. _T.otal leakage.plus losses DurationofTest(Line6minusLine1) a.

Line 4 h

e

-Line 1 h_a Line 22 h_ae min b.

Leak Rate (Line 21 d'vided by Line 22)

Line 21 l

l 9.0

i 1303 1.1 qv 3 144 Meviston 4 Line 23

• Line 22 _ e som QM,Et Line 23 tme11 act e=ceed 19 e 'see 43eeotence critecta 7,4) 7.

Sress Leek Rate a.

Mess change in RCif 2 e-DT Is A-Ve<Tfc. *J T W :r i :

~

(Line 5 minus line 10 a 3540 Ins / volt)

Line 5

/

43 A Line 24 y a 3846 lbm/ volt

• _1be D.

RC37 change in gallons (Line24timesLine18)

I, g

Line 24 _

mLfne 18 (Conversion fsetor) l LLar_t1

=

sal c.

Operater caused changes to the RCOT kiBR H (from date sheet 1103 '.1.3):

sal d.

Gross RCS Laskege (AlgebratesumofLinesII.25and76)

Line 21 _ Tetal RC3 Leekage + Losses Line 25

_ Ctif increase (constdered RCS losses)

R Lfne 28_RCDT c9ance by operater k188.E.

J1 Gross RCS leak rate (identified and unidentified leakage) e.

(Line 27 divided by line 22)

Line 27 Lfae 29 eLine 22 e

osa QME: Line 28 thall not exceed in p.

($ee Accentance Criteria 7 !)

w

_-_ - _10.8

Ihl.1 b

paae 5 od 5 10/14/75 8.

Corrections 'Itentifled leakege) 4.

Iveserative losses.51 gem t.

RCNmp Seel 83 Purge *.29 con c.

Identified leakage -

osa (sten is ateus)

(from dets sheet 1301 1.1.2) ktne 79 Total (Algetretc sum) equi t.

Not unidentified RC3 Leek Rate Algetrete sum of lines 29 and 29 Line 25_

Line It _

k15.2 g: Line 30 any not exceed 1 een (See Accoot:a;e Critaria 7,2 and section 6.4 for setten) l l

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p.ie :

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• till OAfA $N(PT 1101.t 1.1 ?

For yte unee Comestee is ot nyattable inttfel Castittoeg. To be taken et one almute Intervess 4tta 94nel 4 tat i t it fi M211 7Ime

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2 U33,.1 feve 40 e

+.1 UgL1 Pese level 17 -

e ele ugli 4 fest il

+ -

+

e e le_

u!1,j 4tti m

.1 Final Candittent. To be taken at one minute intervalt Mleh 04nel Point fg 79 T.

M3Li fte ige _

URL,l, f4ve 4_*

e, _ e ls Mg,A PeerI,evel 17 _ +

+

e _ eie_

UgL1 4 fank 15 ete M

MST m

+_e e_,1.,_

Cautioni Wen veing poten Panel voltage. De sure to revert the voltage seleetty (* se =) and treat this as an sleetesta sten.

12.0

.4.a....

eat 2;leil Page 2 of 5 NOTE: Carry Algetretc Signs Througn all Steps 1.

Volume cnange due to RC5 temperature 4.

Temperature conventons

1) Initial temperature (570 minus. Itne 2 times 5):

8 570 7 - (Line 2 al) =

ef

'fne 11

!) Final temperature (570 minus Itne 7 times 5):

l?0'F - (Line 7 al)=

f i

r L12L.11 n.

Initial Density (use Line 11 and figure 1 3

L13L11 te detemine donttty) _1Wf1 c.

F1M1 Denstly (use Itne 12 and figure 1 3

L1 1 14 le detemine density)

I W ft

d.. K3 #1 Wine thenge (1tne 13 eines Itne 14. times 10.873)

Line 13 41ne 14._

M 10.473 ft3 a_e_.

8.

Volume thange in Petr lent (Line3sinusLine8a120.8)

Line 3 _

4tne le k1BL11 120.8 I W in a _ ina Ibn 3.

Volume thange in 141 fank Lent (Line 4 minus Itne ti times 250)

Line 4 4tne t-Line 17 250 l W in :

inn its 13.0

.I.),-lI, $ :h[,'.flS$h.'T &./ $ h t k,?h

'l yy

• ~ '

aev t e en ;

r g,1 or5 a

g u 2 - 1975 4

Total RCS 9 ass change (Algetretc sun of itnes 15, 16 and 17)

Line 15 Tave cnange of mass Line 14 Pressuriser mass change I

Line 17 4UT mass change Line 18 Its 5.

Total ACS change in gallons a.

Meen Tave (Line 11 plus Line 12; e 2)

Line 11

1. F Rine 12

1. F Line 19 e to 8F t.

Use figure 2 and line !g to find M

converston factor from ibn to galleast cal /Ibs K3 Investery change (line 18 times line 20) t.

-Zj Line la 1hn Line 21 aline 20 sal /1bn a sal d.

Operator caused changes to system M

(from data sheet 13031.1.3):

sal e.'

Total ACS testage plas losses

~

(Algehraic sum of lines 21 and 22)

Line 21

• 1ine 22 Line 23 eat.

8.

Total leakage plus losses a.

Duration of test (line 6 minus fine 1)

Line 8 h

a

.Line 1 h

a Line 74

_h mo min 14.0 sk,'

.I idm u-

e,.p g.e,4 Page A of 5 I

4 FAY 2

• 1975 n.

Leak rate (Itne 23 divided by line 2A)

Line 23 Une 21 eLine 24

_y ope l'

g: QOS thall act estee410 op flee Accentance Criteria 7,8) 7.

Gross leak rete a.

Mass change in RCOT (Line 5 rdous line 10 x 1540 lbui/velt)

Line 5

-Line le M

v a 3340 lbm/velt a _ 1bn t.

RCDT change in gallons (Line N times Itne 20)

Line N attne N (Conversionfacter)

j M

=

eel 1

0 orater.ae.e.. - t,e M

(fromdatasheet 1341-1,1.3):

set d.

Gross RCS leakage (Algeteste sun of Ifnes 23, 27 and 28)

Line 23 Total RCS leakage

• 1 esses o

Line 27 RCOT increase (considere 4CS losses)

Line 2f RCDTchange(byoperator)

Lf M I

• JS1 e.

Gross RCS leak rate (identified and unidentified leakage)

(1tne 2e divided by line 24)

Line 29 _

Une 30 eLine 24

=

em 15.0 l

)

^-

..y. 3,,. 5 Dage $ of 5 10/14/75 QM[J,: Line 3n small not onceed to e r.

Itee Acetstance Critwata 7.1) 8.

@ rrections (identified leakage) 4.

Evaporettve tosses.51 g p t.

RCPuno Seal e3 Purge +.28 gem c.

Identifft? Leakage -

o p (sign is negative)

(from data sheet 1303 1.1.2)

Line 11 Total (Algebretc sum) gen 9.

%,t unidenttfted RCS Leak Rate (Algebrate sum of Ifnes M and n)

Line M Line 31 Line 32 esa LIMIT: Line 32 nov not exceed 1 ene, (See accootence Criteria 7,2 and section 6.4 for action)

Romerts:

DYM Model #

Serial #

nnemed~ by Date A90 roved Dy Cata 16.0

57 1303-1.1 Revision 4 MAY 2 1875 Data Sneet 1303 1.1.2 IDENTIFIN LEAKAGE 1.

Seurte of Leakage (Descelbe in totall, attaca drawings if necessary) 2.

Method used te determine leak rete (Describebriefly) 3.

Leak Aster oss (For use in step s c of Data Sheet 1303.1.1.1.1 a W 1.1.1.2 FiRMw onte 4

Possible Safety Isolications (ShiftSuperviserCheckOne)

Yes (!nitiate necessary ac 4

Ne Esplain Shift Supervisor Date I

17.0 g-- -

~-

SP 130301.1 I

Rev t l f ori 4 I

WAY 3 istl l

Otta sneet 1303 1.1.3 QPERATOR CAUSED CMt3 TO RC5 INVENTORY 1.

Identify eserettei that caused change:

i l

2.

7tme Geeretten Started: __

Time Geeretten Geseleted:

3.

Calculattens 4

Total change to RCS inventery:

sal.

II0fts: 1)

If change is to RCUT entre in section 7 of Data Sheet 1303 1.1.1.1 and 1303 1.1.1.2 2)

If change is to any other part of the system, enter in section 5 of Data Sheet 1303 1.1.1.1 er 1.1.1.2 3)

M Reuevels from the system have a negative (-) sign, l

i Addittens to the system have a positive (+) sign.

1 Performed By Dete

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E 1303-1.1 Revision 6 i

1 02/17/76

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ENCLO$URE 11 Computer Determination of RC Leak Rate E.2.1.0 M

This program is designed to perform all the calculations accomplished on Data Sheet 1303-1.1.1.1. The plant computer will automatically gather all inpues and average three minute intervals of the initial and final readings. This program is run from the programmer's console of the Sailey 855 coseuter.

It may be run at asqr time the programmer's console is not being used by another program.

E.2.2.0 PROCED@t j

E.2.2.1 Turn en the programmer's selectrie: typewriter next to the Is11ay 855 computer. Se sure that the "OUTpuf SELECT

• switch is on " UTILITY CIMPUTER."

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E.2.2.2.1 If the computer printout on the selectric shows a question mort (7), type "r". then depress the " Return" Key. The computar vill respons with an esclamation mort (!).

proceed to E.2.2.2.2.

i t.2.2.2.2 If the printout on the selectric shows an esclanetton i

mark (1), type "RC" and then press the

• Return' key.-

(See sample printout: Attachment 1)

E.2.2.3 The computer will then request the ti e interval over j

which the tast is to be run. Any interval from 1 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> in one hour intervals may be choosen. Enter a single digit, then press the " Return" Key.

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• e 1303 1.1 Revision 6 02/17/76 E.2.2.4 The computer will now request known leakage. Enter

"!aentified Leekage" (as determined by Data Sheet 1303-1

'l 1.1.2) in gallons per minute. Enter operator caused changes to the RCDT or the RCS (as detailed on Data Sheet 1303-1,1.3) in gallons.

M: For the above en*>1es. be sure to enter a decime1 point. If no decimal point is entered.

the computer will fasert one according to the.

forest it espects to see.

E.2.2.5 The computer will now print out all required data. Be sure to attach data sheets detailing any entries made in step E.2.2.4.

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1303-1.1 Revision 6 02/17/76 1

ATTAC)#'ENTl tre OATE: 01/20/75 TIM: 14: 3:38 REACTOR C00LANT LDMGE TEST SP 1303-1.1 DESIR S IN DVAL (1-4 HOURS) i

. /.

+

ENTS 100ff!FIED LEAKAGE FRM 05 1303-1.1.2 (GPM)

!,h V,.,

DITS ACST CHMSE (GAL) i '.'

DITS ACS CHANGE (GAL)

TDE TCA TNA TC3 Tie TAVE PRZit LVL MUTK LYL RCUT LYL T.,

(F)

(F)

(F)

(F)

(F)

(!N)

(IM)

(VOLT)

Ya'),.

14: 3:54 554.977 801.085 556.250 400.719 578.7S0 238.311 79.803 8.925 16: 8:54 557.031 801.070 556.180 400.719 578.742

-ka.

230.178 79.095 s.945 j.'];

LEAGGE'PLUSLDSSES(<30,GPM):

0.0473 GPM 3;..

M RCS LEAR RATE (<10 GPM):

4.1443 GPM d'

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h "T WIO G TIFIED LEAK RATE (<1 GPM)

-0.2763 GPM

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