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Commonwealth Edison Company ONE FIRST NATIONAL PLAZA * CHICAGO, ILLINOIS

~\,

Address Reply to,

POST OFFICE BOX 767 *CHICAGO, ILLINOIS 60690

October 10, 1972

Mr. Ailgelo Giambusso Deputy Director of Reactor Projects Directorate of Licensing u. s. Atomic Energy Conunission Washington,. D.c. 20545

Subject:

Dear Mr. Giarnbusso:

Results of the Primary Containment Leak Rate Test for Dresden Unit 2, AEC Docket No. 50-237, DPR-19

The Dresden tlhit 2 Technical S~ecifications, .section 4~7 .• A,: requires a .Primary containment leak rate test at

· var·ious times during the ·first ten. years. of operation. · . The I .

results of this test are required to be reported by Section 6.6.E.3 of the same Technical Specifications. Attached are the results of the primary containment leak rate test per.formed· ¢hiring the second refueling outage of Dresden

· Uniti :4 .: This test was conducted from April 25, 1972 to April 27,' 1972.

In addition to one signed orig~nal, 39 copies of this report are provided for your use.

Very truly yours,

L. D. Butterfield, Jr. Nuclear Licensing Administrator

:~. - - _. - -- - :: _:_· .

', -. ~

··:. ' '··

- . .___..!

• SUMMARY TECHNICAL REPORT OF DRESDEN

NUCLEAR POWER STATION

• Regulat°.!1..

UNIT 2 PRIViARY COfI'l'AINMENT LEAK RATE TEST~:W.ffe.f~i~(tQ;«Q:~~ • ~ ... 1 .... ..-~ ........ ~ •• ~--~·--.~~..v.·

This is a summary technical report describing the integrated leak rate test of the Dresden Unit 112 Primary Containment, which was conducted from April 25, 1972, through April 27, 1972.

The report is divided into three sections:

Section 1

Section 2

Section J

Section I:

Results of Integrated Leak Rate Test at 48 psig.

Results of Local Leak Rate Tests.

Test Proce 15ure, Instrumentation and Uncer­ta.inties.

U . "? m.t /f ..... Re ~rn l ,cs ------

Containment Leak Rate Test

On April 2 5 tLrou;h P.;:.ir~i 1 ?.? , 197?., the Unit #2 Primary Containment Leak Rate Test wa{3 corn'..ucted as required by Section 4.7.A of the Technical Specifications. The test was ~onducted in

\ two parts:

a) A 24 hour pressure drop test at 48 psig.

~} A 4 hour pre3sure drop test with a calibrated induced leakage at 48 psig.

Prior to the test and follcwin~ pressurization, sufficient ti.me was allotted to &llc)w all Lc:nperr:~ture;:; to st2bilize. Calcu­lation of leakaDe rate included ccr·~·· 12ctiot! for 2ny d1anges in temp­erature and hwnidi t. y tl;rGlJ.:~hout t,i·, [.S teE:.t. Ac tue.J. dryi,·leil pressure was converted to dry c:.ir pressur·•::' by ~:oubtra.ctirz the calculated vapor pressure, 1·rLich •:ms ·i..!2sed cm tcmp<::::rc.tL:re o.na humidity meas­urements.

a) 24 ho~r test at 48 o~i~

This test·1{as perfozned from 1:00 fam. on April 26 through l ·OO o 'r ~1 "7 '1·'i. - '·o"···-1 l,..,,.,,,~.·~-, (''J' o·'t of· tl- 0 pr1·ma·,,-• Peffio D Ji..,r-'- ,:_ • Jl\:: '·' 1.•c: .• _ ... •::.s•tq;J.t:: .LiTl L~(Jj 1.U .<:, I lJ containment v1a~ cal c1~la t.ed to bl" 0. 3015 \.,s·i;;ht percent of the con­tained air over the 24 hour te.st per·i.oci ( 0. Cl26 wt.;; per hour) vrhich is well within the ~'echr.ic:::•.1 S.;_.er,if:i.c<.>.tio;1 lLnit of 1.2 weight percent (0.75 x Lt, 0 (Li-8)) of' ~.he cont;;:Ln~~c~ .::d.r per .?.4 hours.

April 27,

b) 4 hout test, with induced i02ka7e, @ ~.8 psig

l

5:00 p.m. on the adequc.cy of

Z'ff,Z,,

- -~-'.\

.. ' • • the test method and instrumentatt6n:to "s~e" .a leakage rate equivalent to that calculated during the 24~hour ~est. The induced leakage rate was 2.6 scfm, or 0.0129 weight percent per hour, making the total leakage over th~ period 0.0255 weight perrient per hour. The calculated leakage over the four hour test period was 0.0615 weight percent per hour, giving a percent error between the calculated and actual leakage rates of 141.2% error. The accuracy of the four hour test is limited, however, d.ue to the short test. duration.

c) Corrections from local leak rate tests

As explained in Seqtion II the results of some of the local leak rate tests and the repairs to these penetrations required the addition of 10,-008.071 ~cfh leakage to the integrated leak rate test. The corrected leaka~e rate after the additions was 20.1135 weight percent per 24 hours, exceeding the Technical Specification limits.

Section II: Local Leak Rate Tests

'Prior toithe. contaim1ent leak rate test, all testable containment penetrations were individually tested for leakage, and all ·but f,our of these were r'2corcied ,,,ithin allowable limits specified in License DPR-19, Section 4.7.A.2.f of the Technical Specifications.

The method establi::3hed for acquiring data for the deter­mination of penetration le2kage rate::e 1·12,s the standard method em­ployed in previous local leak rate· tE)sts. In all cases, leakage was based on measurement of pressure decay at pressures specified in the Technical Specifications.

The test proc8dure used to obtain ~ leak rate ·ror the main steam isolation valves varied slightly from that used iri the other penetratior:s. Tho results 1;Iere obtained by establishing a

t th 25 • 'T . "t )'.~"d. Jl•""\c·t'• ,,.,:;, f' ·'·\ '• ,. ·, ' d ~1 grea er an ps1 6 Hc., er "':•c. ,, ..... .::-... ) •. e,"1'" o,_ t,,_1<:; .:..nooar vci ves, pressurizing the volume betwee~ the valves, and ~easuring the re­sulting leakage through the outboard valv2s. Once the ou~board· valves were tested, the water head was removed, the volume between the valves again pres2urized, and anott~r leakage rate calculated. The inboard valve }.ea~:a0e ; 1as, ther,, t~:e _diff,3rence between the second leakage rat.8 c~1lculated and the 1eo.kagi2 calculated through the outboard valves 0lone.

The maximi.li~1 1 -'e~·; .; ~>~<Lble 1eai·~a1i;e r<::~t(':E:; for each type of penetration and tl:e v.::;l.u:::s o:;tair:cd as a. result of the local leak

. rate tests are shm·.;n .:..:·: 'i';:~;:iL.~ l. 'I'Le totc:Ll lec-1irnge for all pen­etrations is surn.n1?.rizeci in ; 0 ~<-~nc.;:c·:~· ct:.tic fc:ct p·.:.r hour and repre­sents the results of the local leak rate testir~ prior to the integrated test.

a) ·Personnel Air Lock

Initial testing of the

2

')t::r·so!n:el 1:c.•::.::k ir;,_i.icated a leaka.;e - () )... -~ ~ .....

. ~-~. -r

•• • ·rate of 134 scfh. The source of the leakage was traced to the exterior upper hand wheel stem seal. Following repairs prior to the integrated test, the leakage was reduced to zero. Since the airlock exterior door remained open during the integrated test, repair of this leakage had no effect on the test results.

b) Torus/Reactor Building Vacuum Breakers

Initi~l testing- of the piping between the torus/reactor building vacuum breaker valves A0-1601-208 and 1601-318 indicated a leakage of approximately 17,000 scfh. Investigation indicated tha~ the leakage was through A0-1601-20B. Following repairs, the leakage rate through the two valves was calculated to be a.071 scfh. If it is assumed that repairs h&d not been made ar.d that all of the 8;071 scfh leaka~e was through the unrepaired valve, then the leakage rate of 8.071 E".cfh must be added to the integrated leak rate test results to account for any possible effects of the repairs made.

c) Primar·; Cont2inment Fur ;r.e Lines

Prior to '.::.}1e ref;2elirE outa~~e, excessive leakage through valves A0-1601-21 and 22 \·1:1s _ :i~~OH:recl, rec;uirir\; t~1e purge line inlet to be blind flanged. Tne ~ea~age rate was estimated to be in excess of 20,000 scfh. F.:JlloHinp: repairs to t!·1e -valves, includ­ing replacement of <"- third v.::;lvc in - the line, A0-1601-56, the leak­age rate was calculAted to be 14.89 scfh. Assuming the worst case with ~ of the total lcc:tka.;:_;c flo11inc; throu2;i1 each of two valves, approximately 10,000 scfh le2kage has to be added to the integrated lee.k rate test result:=:-; to corrr-:ct for any· effects of the repairs rnade.

d) Feedwater Check Valv8s

Both 11 B" line feed1vDter cLock ii·.:::.lves ezhibited excessive leakage during the local lE:ak rate tests.. Both valves, 220-58B and 220-62B had a leakage rate of 5000 scfh. Since the feedwater lines were flooded during the integrated test, th~s leakage would not have appeared in the leak test result~. However, except under several coincident improbi:J:il.::: occurrences, the fcedwater lines will remain full of water. 11 0 correction for this leakage will be added to. the integrated :i.ee:k i"ate ter::.t re::.-rnlt:::..

T1w results of the i.nte;,:;r·c.tec~. le:;k re.ts test, .:tfter cor­rections, indicate a leaka~e rat8 of 20.1135 wei~ht percent per 24 hours, grea.tly exceec:Li.:\.~ tLn 'l\?chn.:' cc.l S1;ecii'ication Limits.

Section III: Iq:..E:.£;.tB t.ed _Lcak r~atr:: Test Procedure, Im:. t.r·:ur:1c1! t·.a t.,i on ;: .. _n( Ur:ce.rtaintie s -- -

Tl-Le test met!wd er:;plo~y"ed for the Unit i/2 Drywell and Pressure Surpression Co~1taj.'11n1ent L0a.k .f{,::;t.e 'le:::;t v,;ci.s the absolute pressure-tempere.ture ;nethod. Th:s method j_:; in &L~reement with the

3

. .

?, •

"AEC Technical Safety Guide, Reactor Containment Leakage Testing and Surveillance Requirement", dated December, 1966, which permits either the absolute pressure-temperature method or the reference vessel system method in accordance with ANS-7.6 standards.

'.\

The leak rate test was conducted at one pressure level, the calculated maximum peak accident pressure of 48 psig. The duration of the test was 24 hours.

. Closure of containment isolation valves for the test was acco~plished by normal means.

The leak rates were calculated using the following formula:

L, fa=lOO rl- T1P;i

L T2PU

where L,%= Primary Containment Leak Rate, %/Test Period

T1 = Average Containment Air Temp. at start of test, OR

= Average Containment Air Temp. at end of test, OR

P1 = Dry Air Pressure in Containment at start of test, mm of Hg

P = Dry Air Pressure in Containment at end of test, 2 mm of Hg

T1 and T2 were calculated from the average of 27 copper constantan thermocouples located inside the containment such that each th~rmoco~ples represented approximately 4% of the total containment volume.

P1 and P2 were calculated from the difference of t~e total absolute pressure in the containment as measured on a mercury manometer, and the water vapor pressure in the containment is calculated based on four dew point cells located in the containment.

Figures 1 and 2 show the locations in the containment of the ther­mocouples and dew point Gells used in the temperature and water vapor pressure calculations.

Appendix "A" contains a copy of the instructions provided to the data takers during the tests and copies of the completed data sheets for the 48 psig te$tS.

As indicated by calculations in appendix "B", the calculated measurement uncertainty of leak rate was .:!:. .095%/day for the 48 psig test.

~· ---- "::_."

- - - ---~··---- ··'•'.

• TABLE I

LOCAL LEAK RATE TEST RESULTS

Double Gasketed Seals

To·t·a1·:· Measured

10% Lto (48) . 0.968 scfh

Testable Penetrations ~nd · Isolation Valves

30% Lto (48) 161.403 scfh . '·'

Any one penetration or .Isolation Valve except Main Steam Line Isolation Valves 5% Lto (48)

Main Steam Isolation· Valves

Total Allowed

% of Allowable

58.7 scfh 1.65

176.03 scfh 91.56

29.34 scfh 70.11

11.50 scfh 68.17 /valve

:::' !1Iaximum ineasured leakage on an i ncJ.i vir.iua 1 penetration/valve.

5 -t 9{, b

} .

APPENDIX 11A"

1. Record the following data hourly:

a. Ambient temperature.

b. Barometric pressure.

c. Drywell and pressure suppression chamber pressure from gauge.

d. Scale 'reading Hg. r.1anometer.

e. Temperature of Hg. manometer

f. Air tempe ra.tures inside dry.1"ell and pressure suppression chamber.

g. Dew point temperatures inside drywell and pressure suppression chamber.

2. The following plots are to be made in the field at the time of the test.

J.

a. Average temperature of the contained air versus time.

b. Dr].ve 11 and pressure suppression chamber air pressure versus time.

A table of reduced data, having columns given below and is to be updated every age rate test.

ColumnITJctay

~o. 1 ~hrough 19, are t:'J:::c during the leak-

Column/ 2jhour

Columr{Dambient temperature = temperature of Hg manometer (°F)

ColumnG'Jtemperature of Hg manometer (°F)

Column[}Jcorrection .facto"F-.-4_or mercury ,m2.r:ometer: = -0.000100452 x~ l.00322462l{figure No. 3)

Column[§Jbarometric pres.sure c:.s re;;.c1 from manometer (mm of Hg)

Column[Z]barometric t·r1-:'ssure (mm of Hg at zero 0c) =[I)x~

C l 161 1 ,. f' .. b' t .... o· um11~sca e reac11n.s c'.:.. i-:;:; n1a1lo1neter at a1n ient emi..:eravure (mm)

coiumnl _:J~i~g~~~;; :m:r1 ~~~3;;4~~~10~;:;:: No. 3

J

6

. - ~·- - -~ z,9 ( / 1 p._··· ~- - -

-2-

Colllinn )1oltotal absolute pressul'.'5 in vessel including water vapor pressure (mm of Hg at 0 C) =~x[2]

Column j11j average temperature of torus ( °F) = -k x ~.(readings @ Tc)

.Column lt21 average temperature of drywell (°F) = 1/23 x~readings @Tc .

Colflmnj13I ~rage temperature of containment volume (°F)=· o. 557 x ~ +. 0.443 x j11}

Columnj14lwater vapor pressure in torus (mm of Hg)

Read from the table of ts:·:r;:Jr,~ratures and pressures at ·saturation shown on pagE>~. Temperature Tl defined below is to be used to encer the table.::<

I(;

Tl=@- ( (Te-2)-(DP-5)+(TE-6}-(DP-6)) .. :< ·:' .

. 2

Column j15Jwater vapor pressure in drywell (mm of Hg)

Read from the table of temperatures and pressures at . saturation shown on pa.ge 12. Temperature T2 defined,, below is to be used to enter the table.

. . . . · · .. •

T2~ - ((TE-4)-PP-1) }+( (TZ-7)-(DP-2) )~(TE-22)-DP-3) )_+( (TE-18)-(DP-4))

Column l16laverage water va.por pressure in the total containment volume (mm of Hg) = O. 557 x l15j + 0.1~43 x j14I

Column j17j dry ai:, ~r;ss:rh( absolute) ,i,n ~r~e--to~al containment . volume at tem.c.e1 a .. uri::, l'.:2J (mm of Hg ~= 0 C )-~~ .. · ... ·. . .

Colu..rnn j1sl hourly indication of leakage rate (percent)·

L, 11cr= ( 1- ( 11 L rt!vig_us hour + 0 R) x 1,.., 1~t current hr) } xlOO ( 3 ·~~ current hour -r Offrx 7 l:! previous hr f ·.

::: If DP-5)TE-2 arid TPaj6)TS6, then ah' :i.n tor•1s is assumed to be saturated and Tl = 1 •

7

·,\

/ /

Page A4

Derivation of factors used in weighted averages

Total volu.~e of drywell -Misc. steel volume -Concrete slug volume

158,236 ft3

Total volume of suppression chamber -Misc. steel volume -Volume of water 10~ 1 ~98 ft3

125,850 ft3

•

Volume of vent lines between dryvrell and suppression chamber included in []]

Total volume CE] + ~ + [£] = 284,086 ft3

Percent total free volume drywell for total containment.

% = 0/[D) = 55.?r~ Percent total free vohune suppression chamber and vent lines for total containment.

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2 ('""" \- "L

4p ......

3-1-

5"" f'""' 4-5

1 p.m. 4/26/72 to 1 p.m. 4/27/72

Total leakage per 24 hour test period 0.3015%/day

Average leakage per hour test period 0.0126%/hour

4 HouR· \€5\

w I \ 1'\ D v c.. t::.. a. . L. E'. A \<::.A.G. E:..

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+ o. 2 2.'12.

- o.oo5D

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4 hour test period: Test pressure 49 psig

Induced leakage 2.6 scfm or 0.0129 wt. %/hr.

1 p.m. 4/27/72 to 5 p.m. 4/27/72

Total leakage per i, hour test period 0.2463%/4 hours

Average leakage per hour test period 0.0615%/hr.

24 ..

• APPENDIX B • UNCERTAINTY IN MEASUREMENT OF DRESDEN 2

PRIMARY CONTAINMENT LEAK RATE

Computation of Leak Rate

L, % .,. 100

where: L, % .,. Primary containment leak rate, %/hr. T1 = Avg. air temp in primary containment at last hourly reading, T2 = Avg. air temp in primary containinent at current hourly reading, P1 = Dry air pressure in primary con ta inmen t a last hourly reading, P2

.,. Dry air pressure in primary containment at current hourly reading.

The uncertainty, or standard deviation o-(L), in the calculated value of leak rate is determined from the variance:

= T1 Pz ;

T2 P12

l. Uncertainty in dry air pressure:

Pory Air = Pbarometric x C.F. - PHzO vapor

Manometer JM50Gl30BV2B, S/N ll-199A (page 26 and 27, Pre-Op A-1) has 0-3302 mm and certified accuracy of ±0.1 mm. readability is ±2mm. Then

a range of Assume

=

= ~

Eo.113302)2 + (2/3302)~ 2

0.06%

25

lj .,

z91. t?

·..;j ... ·~ . ' r •

2. Uncertainty in Avg. air temperature in primary containment

Accuracy of thermocouples± 40 or± 0.7%. Assume± 1% accuracy of readout. Thus a- (temp) = ± 1.2%

Avg. air temperature in primary containment, T, is calculated:

T c O. 557 T Drywell + 0.443 T Torus

~ (TDrywell) = ~3(1. 2%) 2 J \ = 5.8%

o-(TTorus) = [ 4(1.2%) 2 J ~ = 2.4%

Thus O"' 2 (T) = (0. 557) 2 (5.8%) 2 + (0.443) 2 · (2.4%) 2

o-lT) = 3.4%

3. Evaluation of uncertainty in primary containment leak rate:

~ 2 (L) = LdL )2cr

2CP1) + ~tfL )

2a-

2(P2) + ~oL ) 2

a-2

(T1.) \~Pl JP2 t\T1 .

,.

For small leak rates:

= -Tl -1 --T2 P1 P1

o-2CL) - (l/P1) 2 x (0.06%) 2 + (-l/P1) 2 x (0.06io) 2 + (-l/T2) 2 x (3.9%) 2

+ (l/T2) 2 x (3.9%)

26 -· -;_::_ ._ ._ -· ..: .-.~· - .-~ .. - .

, ~;r • • For 48 psig Test: Pi~ 3230 mm, T2 ~ 554°R

• •• o-2 (L) = . ~/ ( 3230) 2]

= ~/ (3230) 2]

(0.06%) 2 + ~/(554) 2 J (3.9%)2

(l.94mm)2 + ~/(554) 2 J (19°)2

= 1.9 x lo- 7 x 3.8 + 6.5 x lo-6 x 361

= 1.2 x 10~7 + 2.3 x lo-3

~. 2.3 x 10-3

cr-<Li8

= 4.8 x 10-2 = o.048%

:. L = 0.3015% ± 0.095% or

3653 scf/day ± 1163 scf /day

27

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