Text

Integrated Leak Rate Test of Reactor Containment Bldg
	ML20147B668
Person / Time
Site:	Oconee
Issue date:	09/29/1978
From:	Davenport B, Rogers R; DUKE POWER CO.
To:	;
Shared Package
ML15222A046	List: ML20147B668;
References
	NUDOCS 7810110092
	Download: ML20147B668 (50)
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DUKE POWER COMPANY OCONEE NUCLEAR STATION UNIT 3 ,

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L INTEGRATED LEAK RATE TEST ,

OF THE PIACTOR CONTAINMENT BUILDING

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l Prepared By: m;j l

' Rick Rogers [ ]

l Test Coordinator f

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Approved By: '

hm

. G. Davenport Test Engineer p)

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TABLE OF CONTENTS

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SE'CTION PAGE

1.0 INTRODUCTION

1.0.-1 2.0.

SUMMARY

AND CONCLUSIONS ,

2.1-1 2.1' Synopsis. 2.1-1 l 2.2 Test Organization. 2.2-1 2.3 Initial. Test Criteria 2.3-1 ;

2.4 Test Results 2.4-1 :

2.5 Error Analysis 2.5-1 3.0 ' DESIGN INFORMATION 3.1-1 3.1 Reactor Building ,.

3.1-1 ;

3.2 Measurement System . 3.2-1 3.3 Pressurization System 3.3-1 3.4 Recirculation. System 3.4-1 3.5 Ccmputer Programs 3.5-1 4.0 CONDUCT OF TEST PROGRAM 4.1-1 4.1 Local Leak Rate Test 4.1-1 '

'4.2 Integrated Leak Rate Test 4.2-1 5.0 LOCAL LEAK RATE TEST FAILURE DATA 5.1-1 5.1 -Introduction 5.1-1 5.2 Failure Data 5.2-1 -

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- - , . , - . - . . , , . , , . . . . , - . , + , , , , , , - . - . . . . , , - , - , - . , . - , , - , .

1.0 INTRODUCTION

~

C The periodic. Integrated Leak Rate Test (ILRT) of the Oconee Nuclear

/)

'\s,, Station Unit 3 Reactor Building was satisfa'ctorily completed on July 3, 1978. The testing was conducted in accordance with the re- l quirements of FSAR Section 5.6.2.1, Technical Specification 4.4, l BN-TOP-1 (Bechtel Testing Criteria for ILR Testing), ANSI N45.4-1972 and 10 CFR Part 50, Appendix J. The absolute method of l testing was employed with cont.ainment temperatures measured at 24 locations and containment dewpoint temperatures at two locations.

Leakage was measured at half the design basis accident pressure of 4 29.5 psig. A measured induced leak was used to ' verify the l results. Interpretation and final analysis of the test data show results well within the specified limits for this containment, ;

which has a max.imum allowable leak rate of .176% per day. The ,

' leakage rate for Ocobee Unit 3 Containment Building was found to -

be .1029% per day. The mean of the leakage rate over the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ;

test period was .06381% per day. )

I A .

U O e e

Ov 1.0-1 ,

9 w

l 2.0

SUMMARY

AND CONCLUSIONS i

i L f'N 2.1 Synopsis. '

The successful ILRT was performed in accordance with periodic test procedure PT/0/A/150/03 as approved for use on July 8, 1977. This procedure is similar to that used for the pre-operational ILRT.

Pressurization for the ILRT began at 1435 hours0.0166 days 0.399 hours 0.00237 weeks 5.460175e-4 months on 6/30/78 with both air compressors. Pressurization was stopped at 10 psig and the building was. entered and inspected for indi-cations >of leakage. No indications were found and the com-pressors were restarted. The compressors were secured at 0840 on 7/1/78 with the containment at approximately 30 psig. It was noted at 1715 hours0.0198 days 0.476 hours 0.00284 weeks 6.525575e-4 months that the emergency ,

personnel hatch was at the containment pressure (The hatch had equalized with the containment). It is believed the inner door leaked past its seal and equalized the inner l lock of this penetration. This was acceptable since credit is taken for the outer door only.

The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months tes't period started.at 1240 hours0.0144 days 0.344 hours 0.00205 weeks 4.7182e-4 months on 7/1/78. At 1425 hours0.0165 days 0.396 hours 0.00236 weeks 5.422125e-4 months on 7/2/78, inspection of data and calculations indicated that the test was satisfaccory and data aquisi, tion was teminated. The approximate 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months delay was due to bad data at the start of test due to the leaking inner door on O the emergency personnel hatch.

\j j At 2055 hours0.0238 days 0.571 hours 0.0034 weeks 7.819275e-4 months on 7/2/73 a kar,wn leak rate of approximately l- .176% was induced for purposes of verifying the capability to measure a leakage rate. This induced leak rate test gave favorable results. Depressurization of t he contain-ment building was begun et 1220 on 7/ 3/78 and completed at f 0400 on 7/4/78.

l Instrumentation consisted of one (1) precision pressure sensor, twenty four (24) temperature sensors and two (2) dewpoint sensors which were used to measure containment atmospheric j conditions during the ILRT.

l The emergency personnel hatch was locally tested on 7/6/78 with satisfactory results.

2.2 Test Organization The Performance section at oconee Nuclear Station had overall responsibility for this periodic ILRT. The testing activities J

l l

[N l 2.0-1

I i-l were supervised by the test coordinator. See Figure 2.2-1 for organization chart.. The test personnel were' as follows:

l-(p,, ).

1 N- A. Test coordinator -

R. P. Rogers Responsible for all ILRT Activities -

B. Data Engineers (one per shift) -

B. G. Davenport Responsible for Testing Activities on -

G. B. Beam their assigned shifts -. M. Beck i

l C. Data Takers (one per shift) -

L. Heddon l Responsib,le for reading and recording -

D. W. DeNard

! all test data -

G. F. Long .

I D. Computer Operators (one per shift) - T. E. Evans B. Owens H. Thompson E. Operators (normal shift).

i 2.3 Test Criteria s l

Pressure: 29.5 psig j Leak Rate: .176% limiting Condition for Operatir e n

.132% Test Acceptance

() Temperature:

Volume:

60 -100 1,910,000 cu. ft.

2.4 Test Res.ults As sh'own in the computer printouts and graphs in Section 4.2 of this report, the calculated leah rate, the mean of the calculated leat rates and the mean of the measured lerk rates are all well below the allowable leakage rate limit. The leakage rate test results are tabulated below:

Upper Lbnit Of Maximum Allowable Calculated 95% Confidence Test Leak Rate (%/ day) Leak Rate Limit l

l 1

29.5 psig .176 .1029% .132 l .

k-)

s_ -

2.0-2

4 For reporting purposes, a leak rate of .1029% shall be used for this test. This leak rate was obtained by using a least

/ squares linear fit of the 15 min. leak rate data taken during the

. km .ILRT. These calculations are' based on the total time method as '

described in ANSI N45.4-1972.

The verification test consisted of imposing a known leak rate on the containment at the end of the ILRT. Rasults from this supplemental test are acceptable provided the difference between the supplemental test data and the type A test data is within

.25'L . A sunnary of the verification test data is given below.

29.5 psig ILRT %/ day Leak Rate calc. during ILRT, L , .1029 Imposed verification leak rate, Lt .1760 Total .2789 Upper verification limit = .2789 + .25 L g .323 Leak rate cald, during verification test .267 Lower verification' limit = .2789 .25 L .235

,, 2.5 Error Analysis .

t

\m The leakage rate in weight percent per day is computed using the absolute method by the formula:

~

1 - To P Lr = 2400 (

H .

T Po-Where:

Po = Initial Reactor Building absolute pressure corrected for water vapor pressure.

P = Final reactor Building absolute pressure corrected for water vapor pressure.

To = Initial Reactor Building mean absolute temperature.

T = Final Reactor Building mean absolute temperature.

H = Number of hours held at test pressure.

i l* The change or uncertainty interval in LR due to uncertainties in

. the measured variables is given by:

-d 2.0-3

t b

_ gg ,' ~[dLR.a\ + dLR . op + dLR . a + dLR . a t _\ dP p/ dPO j

dTo j

dT

. l wJ ,

Where o is the standard error for each variable.

The error in LR after differentiating is:

2400 -To .e\ +IoP T ,eb + -P .e + top.E\

eLR.= H ,TPo j T Po TPo (T'Po /_

Where: e =a p ep =a

To * "To *T T The' analysis technique, based on equation (3) above, was verified by K. Horoschek and E. Weipport in " Tight. ness Investigations on Reactor Safety Pressure Vessels," Vol,.13, No. 3, March 1961.

For small values of LR:

T2 To, P 2 Po and .

e p=epo, eT * *To .

O Therefore, the equation then simplifies to:

~ ~

g _ 2400 -eP 2 + eP \2 +

-eT)2 +/eT 2 H P P/ T/ T

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\ .

or

~

g _ 2400 2 eP 2 + 2 eT 27 (5)

H "

P T

J Where. p e = error in pressure which accounts for the errer in the absolute pressure measurement instrument (ePT) and the water vapor l measurement system (epy) and where eT = err r in temperature.

ep =

(ePT)

+ ( ey2" (5) I e

PT

= Absolute Pressure Instrument Accuracy Error

= Dew Point Sensor Accuracy Error IdPv k 1

( eg l

(Number of Senr. ors) b dT pj 1*

e = RTD Accuracy Error 7

(Number of RTD's). ,

1 v)

( .

2.0-4

To develop a numerical value for'e g it will be assumed that:

, H = 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months -

I RB mean absolute pressure = 29.5 psig RB mean absolute temperature = 529.7 R (70,F) .

RB mean dewpoint tempenture = 68 F Substituting the instrument accuracy values given in Section 3.2.1 into the above equations yields: .

Eg = + 0.0005 percent full scale * ,

Value of full scale repeatability used.. This number is more significant for the error analysis than the absolute accuracy.

eg = + 0.5 F = + 0.353 F

~

y2 From the ASME Steam Tables at 68 F: -

e h

= 0.00414 psi - .

ep = f(0.0005 psi)2+ (0.00414 psi)A -

ep = + 0.00417 psi e = + 0.07 F *

~ (24) \ ,

Value of full scale repeatability used. This number is more significant for the error analysir, than the absolute accuracy.

e T = + 0.0143 Substitution into equation (4) yields:

~

2+ 2[0.0143 2-eI.R = + 2 0.00417 2400 10 (44.645/ 530.00/

= f,0.0330% Per day g

V T

2.0-5

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({j t e, 1mACTOR BUILDING INTEGRATED \ g, TEST LEAK RATE TEST ORGANIZATION #

COORDINATOR ,

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SHIFT INSTRUMENT DATA DATA SUPERVISOR SUPERVISOR

- TAKER ENGINEER 4

COMPUTER INST. INST.

OPERATOR OPERATORS TECil. TECH.

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3.0 DESIGN INFORMATION

/ 3.1 Reactor Building +

V) The reactor building is a reinforced and post-tensioned concr.ete structure designed to contain any accidental release of radio-activity from the reactor coolant system as defined in the Final Safety Analysis Report (Reference 1).

The structure . consists of a post-tensioned reinforced concrete cylinder and dome connected to and supported by a massive rein-forced concrete foundation slab as shown in Figure 3.1-1. The entire interior surface of the structure is lined with a 1/4 inch thick welded ASTM A36 steel plate to assure a high degree of leak tightness. Numerous mechanical and electrical systems penetrate the reactor building wall through welded steel penetrations.

Principal dimensions are as follows:

Inside Diameter 116 ft.

Inside Height- (Including Dome) 208-1/2 ft.

Vertical Wall. Thickness 3-3/4 (t.

Dome Thickness .

3 9-1/4 f t.

( W

\m e) Foundation Slab Thickness 8-1/2 ft.

Linear Plate Thickness 1/4 inch Int'ernal Free Volume 1,910,000 Cu. Ft.

3.2 Measurement Systems Instrumentation used for the Oconee Unit 2 ILRT is similar te 5at used on previous tests conducted by Bechtel. The leak rate te: ;

measurement system is shown schematically in Figure 3.2-1.

Reactor Building pressure was measured by a Texas Instrument precision pressure gage. The unit was calibrated at the Duke Power Standards Lab before the test.

Reactor Building temperature was measured by twenty-four (24) calibrated RTD's and read on a Leeds .and Northrup Numatron digital readout device. Each RTD was assumed to be representative of a fraction of the total containment volume. In addition to the twenty-four (24) RTD's used for the calculation of reactor Building temperature, four (4) additional RTD's were used to measure the linear plate temperature.

/N v!

3.0-1

Reactor Building dewpoint temperature was measured by two (2)

-(,T Cambridge Dewpoint Hygrometers. The relative location of the

\_,) himidity sensors is shown in Figure 3.4-1. A 0-10.45 scfm Brooks rotometer was used in establishing a known leak rate.

3.2.1 Instrument List Specifications for the instrumentation used for the Oconee Unit 2 ILRT are listed in Table 3.2-1.

~ l 3.2.2 Temperature Sensor Locations The locations of temperature sensors within the Reactor i Building are shown in Figures 3.2-2 through 3.2-6.

3.2.3 RTD and Dewpoint Volume Fractions ]

1 Volume frac.tions were used for calculating the average temperature and the average dewpoint temperature in the containment. These fractions were determined using an equivalent volume for each sensor. The free volume of the containment 9as divided into " cells" with a sensor center in each. Volume fractions are given in Table ,

3.2-2. l l

1 3.3 Pressurization Sy' stem i

\~ -) Reactor Building pressurization was accomplished by two (2) electric motor. driven air compressors operating in parallel.

These compressors, purchased for pressurization of the Oconee -

Reactor Building, also include aftercoolers as integral equip-ment. The discharge from.the compressors passes through a single air dryer which reduces the moisture content in the air prior to its entry into the Reactor Building. The specifications for these components are as follows:

A. Two (2) electric driven Joy Turbo-Air (20V2) centrifigual type air compressors with a capacity of 2300 scfm @ 80 psig.

B. Two (2) Basco size 22048 aftercoolers (Integral to Compressors),

type '"ES" Fixed Tubesheet, with a capacity of 2100 scfm @

14.4 psia and with a design pressure of 150 psig.

C. One (1) Hankison (Model H-15) refrigerator type air dryer with inertial impigement separator, and a capacity of 3750 scfm (100 F Sat. inlet) @ psig.

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3.0-2

5 Three. valves, 3LRT-15,.3LRT-16, an'd 3LRT-17 are used to control

-~s pressurization and depressurization of the Reactor Building.

The controls for these valves are located in the test panel. The

)_ pressurization system is shown schematically in Figure 3.3-1.

3.4' Recirculation System The Reactor Building Air Recirculation System consists of four (4) auxiliary fans and three (3) Reactor Building cooling fans.

The. auxiliary fans take suction through ducts in the upper region of the Reactor Building and circulate it downward. The Reactor Building cooling fans take air from midheight in the Reactor Building and exhaust it through duct work down to the lower levels of the Reactor Building. This is shown schematically in i Figure 3.4-1.

3.5 Computer Programs .

All calculations, summaries, and reports were performed using the Duke Power Company ILRT computer program.

3.5.1 Duke Computer Program The Integrated Leak Rate Program calculates the leak rate for a nuclear reactor containment vessel. The program computes the leak rate at a given time from input values of pressure, temperature and vapor pressure. The leak

()

f-'s rate, as 'a function of time, is determined by elementary linear least-square methods.

The Integrated Leak Rate Program is designed to allow the user to evaluate containment leak rate test results at the jobsite during containment leak rate testing. Interim leak rate test reports may be obtained at any time during the testing period. Each interim report consists of two printouts. The first printout, called the total-time computation, uses the initial and latest input data to compute leak rate. Each computed leak rate is statistically averaged using a linear least-squares fit. Early in the test this method of computation givet indication as to whether or not the leak rate is acceptable.

A second printout, called the point-to-point computation, is also provided. The point-to-point method uses the data at a given hour and the data from the previous reading to compute leak rate. Each individually computed leak rate is then statistically averaged using a linear least-squares fit.

e l 8 U

3.0-3

The results of the two methods used indicate that either method is a satisfactory method for' computing contain-(}/

(_, ment integrated leak rates. ~ Both methods of computing the containment leak rate are presented in ANSI N45.4-1972.

However, the total-time method is recommended by Appendix J to 10 CFR 50.

3.5.1.1 Explanation of Program 3.5.1.1.1 Purpose

a. Process raw data for use in leak rate cal culation.

b. Calculate leak rate on a point-to point or total time basis.

c. Calculate a statistical point-to-point or total time leak rate by a linear least squares fit of the data. !

l

d. Output data, j 3.5.1.1.2 Process Raw Data

a. Temperature 1 p-~

-- (a.1) Unit -

F.

, (a.2) Number - 28 (Includes 4 on i linear pinte). l (a.3) Input to computer will be in F.

The computer will apply necessary calibration corrections to the temperature.

(a.4) Each temperature (28) will be weighted by a volume fraction. l The calculation for the average !

building temperature ist l T = IT .V n n Where: T = Average building temperature, F T = Temp. at each point, n + 1-28. F k -

(,. )

8 t

3.0-4

. . . ~ . . . . .. . - .

. J ')

. .t ;

. V = Volume fraction .

. 'for.each point' . ,

The volume represented- !

\ divided by the total :

volume. Volume fractions l[

must' add to 1. !

t The Average Temperature must be converted to R by adding 459.7.

l (a.5) The. temperature on~the linear plate ?

will be available for output. ;

b. Pressure ,

(b .1') Unit - psia.

(b.2) Number - 1.

(b.3) Input is in psia. The computer will apply necessary calibration -

, correction to the pr, essure.

(b.4) The pressure will be weighted by a volume fraction. The calculation for the average building pressure is: l O . P=W P1 l

Where:

P = Average Building ,

. Pressure, psia. j l

1

. P = Pressure by texas instrument, psia.

W = Volume fractiou I 3

(must equal 1).

c. Barometer (c.1) Unit - Inches of Hg @

, 32 F. l l

(c.2) Number - 1. q (c.3) Input is not used by calculations, but will be available for output'. j

d. Dewpoint Temperature

.- (d.1) Unit - F.

.3.0-5:

, < - - * , - -,.m -

,.44 ,r N + g- g wm y y -ww-,,y-mp.- + , g- 4 1

n ; ,

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

4

, .(d.2) Number - 2. j

~

(d.3) Input to computer will be l . .in F. A calibration curve will :

be associated with each sensor ;

and the input will be. corrected.

(d.4) Each. Dewpoint Temperature is weighted by a volume fraction.. i The calculation for the average is: ;

T v f 3 v1 4 v2 Where: Ty = Dewpoint Temperature, F.

j Tyy = First Sensor Dewpoint temperature, F. S ad Sensor Tv2 = Setemperature,F., Dewpoint I

, W = Volume Fraction (W3+W4*

(d.5) From the Dewpoint Temperature (Saturation Temperature) the Vapor Pressure (Saturation l Pressure) is determined from the steam tables. The range ,

required is 40 to 120 F from the steam tables.

Pv = f (T v)

3.5.1.1.3 Leak Rate Calculations i

a. Leak Rate on Hourly Basis ;

Leak rate will be calculated on a point-to point basis from data obtained at the previous point readings (data subscript 1) and data obtained at the present point' +

readings (data subscript 2).

(a.1) Absolute Method

~"

11 (P -P *I La = 2400 l--

Wt ,,

2(1 ~

vif 3[0-6 [

i

~ . . , . - . , _ _ . . _ . . .._._ _._ _'l

4 Where in (a.1) above -

- g *s L = Percent leak, rate per hour !

() (La or Lx)

T1 = Average absolute temperature :

of Reactor Building air at '

start of each test period, F.

f T2 = Average absolute temperature of Reactor Building air at end of -i cach test period, F.

P1 = Absolute pressure of Reactor Building at start of each test period, psia.

P2 = Absolute pressure of Reactor Building at end of each test period, poia.

Pv1= Vapor pressure of Reactor. '

- Building at start of each test ,

period, psia.

Pv2= Vapor Pressure of Reactor !

Building at end of each test period, psia.

U.-w

uit = Time interval between start I and end of test period, hours. ,

. b. Statistical Point-to-Point Leak Rate Linear least square fitting is used. ,

to calculate a statistical point-to- !

point leak rate for the Absolute ,

Method. l Li = a + bti I Where: a = 121 I(ti2) - Iti Ifiti N I(ti') - (Iti)' l I

b = NItiti,- Ifi Iti e !

NI (ti') - (I ti)' )

j Li = Statistical leak rate Ai = Calculated leak rate

. ti = Time between data sets 1 i'

, 3.0-7 i

e . - , . - _ _ . _ . ~ .. _ ___ _

N = Number of points to be

.. fit (number of data sets)

(,,/ c. Leak Rate From Initial Data Set Leak rate from the initial data set to each successive data set is calculated by the following equation:

(c.1) Absolute Method ;

J Laa = 2400' 1 - Ti (Pt - Pvt)

TI Tt (Pi - Pvi) l l

. Where: i = Indicates data from )

initial set

'l t = Indicates data from each )

successive set j 1

TI = Time from initial data set.

d. Statistical Leak Rate From Initial Data Set l

The leak rate is calculated by a i linear least squares fit over a !

} period from the initial data set to each successive data set.

(d.1) The equations are the same as in 3.5.2.1.3(b).

(d.2) The data used is obtained !

from 3.5.2.1.3(c). I

e. 95 Percent Confidence Limits l l

CLi = Li + T oi Where: CLi = Confidence limits at time ti l Li = Statistical leak rate at time ti ci = Standard deviation T = Tabulated constant V

3.0-8

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

) $

s 1.

.r T = 1.95996 + 2.37226 + 2.8225.,

(N-2) (N-2)'

Where: .N =. Number of_ data points -

.i ci = Variance. 'l+1+(to-th N

-. I(ti-t)' .

Where: to'= 0 .

t = _1.I ti N

4

+

Variance = ~ I(fi a - bti)2" +*N , .

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INSTRUMENT SPECIFICATIONS k-

_,- Pressure Digital Readout. -

Serial No. 10132 2646 Mfg. Texas Instrument Model 145 i Type Precision pressure gauge l Range 0-100 psia or 100,000 counts full scale

, Stability. 1 001 psi Repeatability 1 0005 psi Resolution 1 001 psi Accuracy 1 015% of reading Pressure Gauge- '

Mfg. Heise Range 0-100 psig Accuracy 0.1 psi Repeatability 0.3 psi Temperature Elements l

Mfg. Leeds & Northrup

.Hodel 81'97 Type RTD, Copper 100 ohms

O Range 0-150 F Repeatability and hysterisis 1 02 F Accuracy 1 0.12 F Temperature Indications for Tempdrature Elements Mfg. Leeds & Northrup Model 245 Numatron Range 0-150 F Reproductivity + .07 F from 60 F to 120 F Accuracy I .12 from 60 F to 120 F and

_I .48 Below 60 F Dewpoint Temperature i

Mfg. Cambridge Model 992-C1 Range -100 F to +200 F Accuracy- 1 0.5 F Serial No. 332 and 333

. 1

.(

j Table 3.2-1 l- .

L L -

Flow Indicator O Mfg. Brooks

\-) Type Rotometer Model 1110-24 Range o to 10.45 sefm Accuracy + 1% of instantaneous. reading Repeatability Better than 1/4% of instrument reading Serial No. 7004-39848 i

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0 Table 3.2-1 (con't)

I .

k _

-VOLUME FRACTIONS

.f m

k Volume Fractions for RTD's RTD # Volume Fraction 1 .03 2 .02 3 .02

'4 .05 5 .02 6

.03 7 .01 8 .08 .

9 . .05 10 .05 11 .02 12 .02 13 .01 14 .02 15 .02 16 .01 17 .05 18 .09

,e 19 .11

( 20 .01 21 .01 22 .09 23 .11 24 .07 TOTAL 1.00 Dew Point Sedsors Volume Fraction Dew Point Sensor # Volume Fraction 1 (Azimuth 100 Elevation 850') 0.4 2 (Azimuth 260 Elevation 850') 0.6 TOTAL 1.0 4

l-Ns Table 3.2-2,

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LEAK RATE MEASUREfEIT SYSTDi . .

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4.0 CONDUCT OF TEST PROGRAM )

,~ .

t 4.1 Local Leak Rate Test -

.-\

The. purpose of the Local Leak testing program was to systematically check the integrity of valves (seats and packing), flanges, pipe and electrical penetration welds, seals and compression fittings that are part of the boundaries of the containment system. These tests, specified by Section 4.4.1.2 of the Technical Specifications, have a combined Acceptance Criteria of less than or equal to 0.125%

of the reactor building atmosphere per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Final analysis of all penetration leakage rates shows that the total penetration leakage rate was approximately 46 percent of the allowable. l 4.1.1 Test Method l All elect,rical'and mechanical penetration, including locks and hatches, were tested by pressurizing to N 59 psig. The pressure, temperature and barometric ]

pressure were recorded before and after the leak test I (duration of test determined by penetration volume) ]

and ,the leak rate determined by the mass difference j method.

I 4.1.2 Penetration Test Results ,

J

.()

Per Technical Specification 4.4.1.2.3, the total leakage from all penetrations and isolation valves shall not exceed .125% of the Reactor Building atmos- ;

phere in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The total measured leak rate from l all penetrations prior to this test was .0576% per l 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Results of all local penetration tests done since the last type A test are given in Tables 4.1-1 through 4.1-2.

l q

1 i

1 l

l l

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l l 4.1-1 l

. 1

i I

4.2 _ Computer Calculations and Results

'fe~s 4.2.1 29.5 psig ILRT ,

The. curves for the 29.5 psig ILRT are shown in ,

Figure 4.2-1 through 4.2-4. Supporting summary data is given in Table 4.2-1.

I 4.2.2 29.5 psig Verification Test The curves for the 29.5 psig verification test are shown in Figure 4.2-5 through 4.2-8. Supporting summary data is given in Table 4.2-2.

e S

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4- LTYPE- B. I.0 CAL' LEAK RATE TEST RESULTS ~ !

' LR %/ Day-

. Penetration Date' -LR SCF/Hr. ,

Elec.' Penetrations 4/18/75 .

.033798 4.25 x 10 -5 '

Type A' 3/26/76 0'

-5 - -

9/21/76' .03275 4.12 x 10 3.46 x 10 -5 10/26/77 .02751 -5 6/29/78 .022139 2.78 x 10 Fuel Trans.-Tubes ~8/8/74 0 - 4 0 r

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-3

.9/21/76 1.8830 x 10 0 11/1/77 2.6868 x 10 -3 -3 6/27/78 1.6201'x 10 0 Equipment Hatch 8/16/74 0

-3 0

8/31/74 7.336 x 10 0 4/17/75 ,

0 ,3 0 ,4 4/14/76 4.492 'x 10 5.65 x 10 7/5/76 0 0

- -5 10/26/76 1.1895 x 10,24 4.49 x 10 11/23/77 1.965 x 10

-3 -5 6/29/78 8.9001 x 10 1.13 x 10 Personnel Hatch 11/15/74 0 0 2/21/75 0 0 7/2/75 0 0 .

1.41 x 10 -2 1/11/75 11.2267 3/16/76- 5~8046 7.29x10[5 O 8/23/76 11/23/76

.050435 21.881 6.34 x 10 -2 2.75 x 10

-3 3/1/77 7.1395 8.97 x 10

-2 8/5/77.. 21.3176 2.68 x 10

-2 10/19/77 - 33.064 4 15 x 10 i 11/23/77 0 0 -

3/28/77 0 0 .

6/29/78 5.2321 6.58 x 10 ,

l

. Emerg. Personnel Hatch 11/15/74 0 0

-3 11/22/74 1.58.9 8 1.99 x 10

-3 8/7/75 2.358 2.96 x 10 12/8/75 0 0 4/20/76 0 0

-3 8/17/76 2.882 3.62 x 10

-3 12/6/76 1.5523 1.95 x 10 4/6/77- 4.0213 .

8/30/77 5.8157 5.05 x 10,33

-12/5/77 2.4588 3.09 x 10,3 4/4/73 1.6309 2.05 x 10 6/22/78 '6.0987 7.66 x id j

., 7/6/78 6.1933 7.78 x.10 NOTE: 1All' Leakage Lest ' Than 10 N Is Considered To Be Zero.

O Table 4.I' ..

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TYPE C LOCAL LEAK RATE TEST RESULTS Penetration Date LR SCF/Hr. LR %/ Day

(

Mechanical Penetration 4/23/h5 1/21/76 1.8159 1.494 x 10

,3 2.28x10[f 1.88 x 10

-2 11/1/77 -

27.73357 3.48 x 10 -

2 6/27/78 35.197735 4.42 x 10

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~~L IFICATION TEST _ . . . .~~
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ML20147B668

Contents

Text

1.0 INTRODUCTION

SUMMARY

1.0 INTRODUCTION

SUMMARY

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ML20147B668

Text

1.0 INTRODUCTION

SUMMARY

1.0 INTRODUCTION

SUMMARY

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: ---t= :==-:2=jac :--tn:-ur. :-- =h' n:r:

= .: 2 _ _. . ;=t= == = : :[.: nn ==:d =n == t

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