ML20085G011

Containment Vessel Leakage Rate Test Absolute Method

ML20085G011
Person / Time
Site:	Saxton File:GPU Nuclear icon.png
Issue date:	04/13/1964
From:	SAXTON NUCLEAR EXPERIMENTAL CORP.
To:
Shared Package
ML20083L048	List: ML20085C449 ML20085C452 ML20085C455 ML20085C458 ML20085C461 ML20085C464 ML20085C467 ML20085C472 ML20085C477 ML20085C480 ML20085C483 ML20085C490 ML20085C500 ML20085C501 ML20085C504 ML20085C508 ML20085C513 ML20085C517 ML20085C540 ML20085C543 ML20085C546 ML20085C583 ML20085C586 ML20085C590 ML20085C592 ML20085C602 ML20085C605 ML20085C616 ML20085C620 ML20085C622 ML20085C625 ML20085C628 ML20085C630 ML20085C633 ML20085C634 ML20085C637 ML20085C805 ML20085C809 ML20085C826 ML20085C835 ML20085C840 ML20085C844 ML20085C904 ML20085C913 ML20085C966 ML20085C973 ML20085D041 ML20085D048 ML20085D052 ML20085D059 ... further results
References
FOIA-91-17 NUDOCS 9110240079
Download: ML20085G011 (14)

Text

- _ . _ _ _ _ _ _ _ _ _ - _ _

y; y' SAXTON NUCIZAR I%PDlDINTAL CORPORATION

~%

l os D-

[ bid]sN%M C-gMContain >f ent Vessel Ioakane Rate Test D

.a:e fhffc. . W *7I Absolute Method a

\

April 13, 1964 x '

y\

.~

I. ,0_5M e et :

The objective of this .tntegrated leakrige rate test is to confir.n that containment

.essel integrity (including the t.ir-locks and penetrations) is maintained.

II. Precautions:

1. Insure th:.t all personnel are out of the containment vessel prior to pressuricing.

2 Proper administrative procedures are initiated to control access to the inc.cdiate area of the contaiment vessel.

3 Anr quipment subject to dre.aCo because of prescurization is removed or adu uately protected.

4. Peraonnel access to the contr.inment vessel daring the course of the leakage rate tecting shall be govemed by approved decompression procedures-(1). For exposures of no bnger than 200 minutes at pressures not greater than 14.3 psig, no intemodiate holding periods or i decampression stops are required provided that the time rate of pressure reduction in the air lock to stuospheric level is not less than 30 seconds.

11I. Test Feu_: .t The test c;uip:aent to be employed _ will be consistent with the specific.tions set forth in reference (4) and includes the following apparatus:

1 One 120 inch manometer for m. .suring the , ssure differential beoween the contniment vessel and the at osphere, uti dng Meriam No. 3 Flui.

(e.g. = 2.95); least division, 0.5 m.

2 One standard precision mercury barometer; least division, 0.1 mm.

3. One Foxboro humidity detector (Deweel) for measuring the partial pressure 0 of water vapor in the containment vessel atmosphere; least count, 0.1 F dew-point te=perature.-

4. Fou. platinum resistance thermometers located throughout the vesss1.

5. Two . ueller bridges for resistance themameter measurements; least division, 0.0001 ohm.

L, One gas flowmeter for mettrin; a controlled leak; least division, 0.1 cubic foot.

• As defined by reference (4) paragraphs 71 and 7 7 and reference (5)

Section XVI, paragraph 3. -

91i0240079 910424 gy PDR FOIA -

DEKOK91-17 PDR '

. ~2 IV. C:nditione

1. We reactor is in a " cold" shutdown condition and the syste:a piping is t.t cabient temperature.

2. The test equipment listed in III (Page 1) ha e been installed and calib~ated.

3. 7ne contaiment vessel discharge tank is open to tha contaituent vessel <

atmosphore. t

4. he covers have been opened on the internal T. . ratio" 'nxes.

5. The con:.rinmer.t vosecl air hre.dlers, the additional storage well fan, and the rod roc = purge fan are operating e.r.? the rod room do:,r ie span. Tae service water and stern supplies to these t.ir handlers will be on for the duration of the test.

6 The equipment access slab on the top of the primary campartment has been rc;ioved.

7. 7ne contaircent vessel storace ucl1 ic filled to the normt.1 operating level and the sit.Ss have been removed.

E. The nuclear instranentation detectors, with th'e exception of one BF3 and one CIC, are phced ribove the wrter line in the storage well. The two reaining detectors are placed in special thimbles to prevent flooding of the detector er. closures. .

j 9. The periscope pressure chamber is pressurized with nitrogen to 12 psi.

10 Integrity of the contrLirment vassel has been established.

11. Secure the instrtment Air supply to the contt.ircent vessel.

V. Procedure:

I;0 C : A review of the integrt.ted leakage rute tests of the cor.taircent vessels for the principal U.S. power and test reactor facilities nakes it apparent that the reference vessel method has predominated over the absolute method.

In spite of the g n ater use of the reference vessel nethod, there is no general agreement that this should bc the preferred j

method. Several discussions of the relative merits of the absolute and referenco vessel methods have been published and the consensus i

of the most thorc gh of these comparisons seems to favor the t.bselutc method. Discussions of these comparisons are presented in raferences 2 and 3.

}

There is no clear advantage for either the absolute or the i

reference vessel met, hod. The absolute mi . hod will be used at the Saxton llucicar Faperimental Corporation Facility.

4 k

i 4

~3-

1. Tne Penclec co prescor #1 uill bc lined up to supply air to the contaiment vecscl.

2 Preccurir. tion s

a. L,creaco tae centaire.ent vessel internal pressure to 3 psi. hhile prescuricing to 3 pci, an inspection (including the penetrations and -

closurce) vill be conducted for signs of gress leakage.

b. If it becones necessar/ to correct for leakage at this tinc, the contain.cnt veccel nay be entered providing the standards set forth -

in Sectica I: of thic proceduro are adhered to. If necessar/,

cc;rac ri*c the ecntst:ncr.t ves:cl and nahe the necescary repairs. N

,( Record all neccatar/ repairs in the test log and repeat step 2.a. 's (

3. Unen condi.iene aro catisfied $ n step 2.a proceed with integrity test j

ty pr:ccuri:ing the conteintent vesec1 to 5 pei repenting step 2.a.

and i' nece . wry otep 2.b. Repeat for 7 psi and 10 pai.

4. 7ne 1cah rate tact rhculd bc initiated after conditions in the contalment vetcel have stabilized (caring the early morning hours USen atmapheric conditient are nost stablo). The contaiment vessel air tmperature should be etabiliccd so that it does not vary by more than a few degrees over a pt lod of several hours. Tne in'tial and final temperature ,

should ai , bc ac near'g the sciae ne puscible but it is me.e important that they be etabic.

);j

5. Zne leak rate data will be obtained every thirty runutes for the re .ai. der af the test which win be t.t least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D 4

6. i; car the completion of this test a " controlled 1cakage" test (3) win be \7 \ 7 conducted by releacing a neasured quanticy of air. This " controlled \

leakage" vill then be compared to tne measured lech go as deteminod frce t

the dr.ta collected at this time. \'

7. Calculate the contai=cnt vencel percent leakage rate usirq: the equations cpecified ir. section VI of tnis procedure.

C. If the calculated percent leakago rate is acceptable, the containment

- vessel pressure will be slowly reduced and the Penelec compressor #1 and assceinted valving will be returned to normal and prcceed to step n below.

9. If the calculttoi percent leakage rate is slight but there is doubt that the results are a fair indication of actual leakage rate, continue the test for an additicnal period of time.

10. If the calculated percent leakago rate is substantial, recheck the contai=cnt vessel valves and instruments for sources of leakaSe, and repeat the leahace rate test.

11 Enter the containment vescel and make a thorough visual inspection for any indict. tion of effects of the presture test or for any other abnomalities which might have affected test results.

4 VI. C .1 = h t' onc & Dit cues M a lhe absolute method of leal: ace rate deter.:.ination it, a direct application of the perfect gan 1:.w. Tno tote.1 lochagc of air durin~

thedifforcnceinweightoftheairinthevessel(wf,thetestperiodisthcn between the taginning

, (subscript 1) and the er.d (subscript 2) of the test.

PyV = sqRT1 and PcV = v2T I2

~

Therefore sq -w2 " ( ) (1) 7ne fractional lenhago is:

= 1 - P712 (M) (2)

The percent leakage per 24 hourc, or percent leakage rate, will be decignated by IR and is expressed as follows, where H is the number of hours of the test period:

2 I2 " k.. (1 plt 2) 100 (3)

P = Pg (hb + ha) = lbs/in2 Pg = specific gravity (corrected for temperature) hb = h.ranetric prescuro - in hg hn a lhnometer height - in hg T = Average absolute temperature The principal difficulty and najor source of crror in deter..ining leakage .

rate is in obtrining an accurate, truly average temperature for the total volume of air in the containmer.t vessel. Moi, only will the average tcperature vary throughoutthetestperiod,butthespatialtemperaturedistributionwithinthek vessel at anyone time might vary as well.

In order to minimite the latter effect, the contain=cnt vessel air handlerc, the rod roo= purge fan, and the operating area air mixing fan will be operational throughout the test, In addition, the primary campartment venvilation and equipment access slabs will be removed to further improve air r.i::ing conditions. This will also improve the heat transfer to the J

. temperaturo measuring instruments a.nd nakes hu=1dity measurements more relicble, 4

l 1

l \

l D j

. e Tr.e appare:.t 1ca'.: age re.to due to chance in vapor pressure can be et.lcuir.ted separt.t;.ly anc then ade:. to or sdtracted fr= the let.h:.co rate ctilculated with er;ntiv.(3), Tc.ia approt.ch e.llows the offect of water vapor to be evalunted indepca cr.tly so that its significance can be deterr.ined. Assuming the weight h' of water vapor is anall co.1pr. red vith the weight of air, the apparent leakage rate due to change in vcpor preas..ro is very nearly

,.'i

• • " 26p* ( Wi-m ) 100 (4) sq or Ifty= hr. 1 ( D1~ D2 7) 1 100 (3) r1 ';2 where IRy = apparent percent change leakage rate per day due to a change in vapor pressure wyy a ucicht of water vapor in containment vessel at beginning of test w;; = weight of ut.ter vr.por in contt.inment vessel at end of test therefore IRC " III " 18V (6) where !J.c = perccrd leahage rate per day corrected for effect of water vapor

. It is possible to have a slight change in the containment vocoel volume due to themal e::pansion or contraction. Unless there is a substantial difference ir. the centairc.ent m cel tanperature from the beginning of the test to the end -

of the test, the cege in shell volune results in a negligible error in measured preent ler.hage rate (?). If necessa./, the percentage of error in percent 14.kage rate which vou d result is given as follows:

,1 error a , 100 l l

34 (72~71)l nW/d where '< = coefficient of thermal expansion o'd/d = fractional leakage rate .

The leakage rate deto =ined from this test will be' corrected by the following c::trapolation factor to detemine the leakage rate at the design pressure of 30 psig.

k = 10 3*,

Pt k = 5 leakage rate tt c):trapolated design pressure 30 psig it = % leakage rate measured at test pressure Pt = test pressure

Referenco 2 uritten b;' the Ecchtel Caporation for the US.CC states that this str:.i;ht linc extrapolttbr. ic cor.acrvative and that a tract extrapolation to hiJn r prctLure could be to ace the .55 power. Houever it does record that one tett s chowr. t. measured leci:r:co that variod t.s the 1.2 pover of gage prescure.

The Ca:: ton Final Safecucrds St. port figure 506-1 shows the contaircent vessel pretcure it. the incredibic event thct the total encrcy of all liquid in t'..e main co:1r.nt s;/t.tc.: could be trc.nsferred insta;staneously to the air vapor

O:ture c nfined in the contt.irc.cc.t vocsci in what is sometimes called "The

- " -- Credible Accident". 7c.e initial pressare rico roaches a peak of

% pcic in cne second. At tif.o 3D st.conds t'..e protouro is belov 13 psig tnd rcu. int belo.t tr.is prect.ure there:.fter. At tinc 25 ::.inutes, the prescure has

/L_1cr. to . psic cr.d fcca c.t.t point on t..v pres;.u o icvels off et LLout 5 pcic fcr the next 27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br />. Thus it is evident that without any e::trapolation the lecktge :ssured during a 10 psig test for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period at Ssxton will be much hir.cr than the leshace which would occur during this maximum hypothetical, ,

cecident.

Usir.; 10 CFR 100 gaidolines t.n allout.ble lenhace of .4% of the containment vessel Odine pr 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> would not encccd the limit of 300 re: to the thyroid ct the cite boundtr/. Tne St.= ton Techr.ical Specifications specify a ccximum IcLecce et.te of .4.; of the not free volune t.t 30 psig per 24 houro, wherons 10 C7R 100 usuid indichte th:.t a le:.ha;e rate of .45 at appr:o: int.tely 6 psig pr 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> vould to sc.tistceter/ cinco the Sctegucrds Report shows the mecn peccsure for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> would be under 6 psic. The technical specification does

..ot give Sexton cny credit for en ec.;ineered safeguard in that the containment vessel was constracted uithcut insulation in order to minimize the prebsure Er.d letkcce in a loss of coolcr.t accident.

2 0

.-.-.-__.--_.a _.-__ ._

= . . _ - _ . _= -

,, j . 6 i

e i i

Tm?..C3 -

l

1. icvin; t:.L1.. of the U.S. ;;:.vy Sivin: l'anun1, Se: tion 1.5,1%VS:GP 250-538,

. i J:ur cq,1959.

!. . F. ... Criffs.n Lnd G. H. D;'cr, Finci Drcft, Reactor Containment Handbook, hchtc1 Oc;porction, San Frcr.cisco, Califorr4:., February,1964. ]

3. L'. J.1;ce.oci: and C. E. DeLogenn, L ak-3:.to Te:tinc of the :.'.SA Plur. Broch .

!.s. etor C:ntairaent Vessel, Lnds Research Conter, Repert !MSA T;; D-1731, l' i

Jul;', 1963.

4. Proposed S cnttif. for L::.haco Rate 7esting of Containment Stractures for .

uclear T.eactors, cubr.itted to Co:::lttoo taS-7, Reactor Components, of the

/J;S Stand .rds Cc=.ittee, June 15, 1962

5. Pro;occi. St.fet;* Stendard for Desi;n, Fcbrication and 1:cintencnce of Steel Jor.: tinner.t Stractures for Str.ticr.c.ry 1 ucicar Power Reactors, prepared by Sub;w:ittee : o. 2, .'.SA Sectier.a1 Co.r.ittoo !;6, Reactor Sctety Standarc.,

/.pril 15,1963.

1 T

I L

1 r t

t

' t I

I

- _ _ _._,_.__ _ _ _ _ , _ # W 947i yg9 gpp_ ,

W-N'*TT'-"V'-f+-ges+wmy96gp, , _ , , _

..-.._.-....._.........--..~...........=......_.....,...v . . . . . , . . . . . . . - . .

rs

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

. v.. ,s a 0 'diDh I DIVISION OF COMPLIANCE Action _ Inf orma tion,,,,,,,,Concurrenc e Review Memo Rnute Slip Comment Note & Return Per Our Telecon File Field '

RE: SAXTON'S PROPOSED 12AK RATE TEST J. R. Stars - Region I Saxton's proposed leak rate procedure, J. P. O'Reilly - Region I I dated April 13, discusses on page 5 the relationship between their specified leak rate at design pressure and a leak H. L. Ernst - Region II rate based on their containment pressure decay curve. You might be interested in knowing that Lester and I are preparing H. D. Thornburg - Region III a proposs' to DiNunno that is based on the same concept.

J. W. Flora - Region IV Their proposed use of the absolute method I is surprising, espectally since their permitted leak rate at 10 peig will be R. F. Sullivan - Region IV 0.13% based on their extrapolation model.

A temperature uncertainty of i l'F results in a leak. rate uncertainty of i 0.T!. in E. O. Smith - Region IV the absolute method. Their use of an imposed leak is certainly a step in the right direction. However, the scatter R. H. Engelken - Region V inherent in the absolute mathed will ales be present during their imposed leak rate and may tend to complicate G. S. Spencer - Region V verification. ,

For comparison, their permitted leak rata R. T. Dodds - Region V based on the " conservative" flow model would be 0.0871, and on a laminar flow model would be 0.16%. However, the A. D. Johnson - Region V differences in extrapolation models are small campsred to the uncertainties inherent in the absolute mothed. -

W, E. Vetter - Region V cc L. Kornblith, Jr., C0tRQ

5. R. Grier, C0tRQ

\

a r.

FRCE: Kornblith Grier Cobb I Denton DATE: April 17, 1964 Reitsauth Nolan ,,,,_,,lo ng Wood

. .,.-...%. .o ,...n.,......,.. ........aq._,,,,j..-.. . . . ~ . . .

. .. g ..< . ..... p p r., ,

. s.  ; /

I

~, . . ,

pj ,.s .

g, s .-

, , 4,

8. Test Specifications: .

i,

n. Ccntninuc..t Periodic Testing

(.

y-(1)(a) All penetrations, and Easketed closurec "s'fiEIT-- -

be subjected at approximately ye'trly intervals { -

to a leak detection test, using a. Halide leak w - - "

detector either separately at 30 psig test presnure or as an overall containment building test, at a precoure not less thsn five paiE.

(b) All equipment access openings shall be subjected 1 to a similar Itak-detection test upon last closure prior to last start-up.

(e) All airlocks shall be st.1Jec+cj to similar lent detection tests et monthly intervals and at last ciceure prior to last start-up.

All detectable leaks shall require repair ud retests.

(2) All isolation valves which provide a potential ccr:munication with the outside atmosphen, in.

cluding the vacuum breakers, shall be subjected, at approximately quarterly intervsls, to e leak detection test using a HaTide~~Mk detector, either separately or ac an overall ecntainment building test, at a pressure not less than five psig. All autocatic controls and instruentation associated with these isolation valves shd1 be tested at approximately quarterly intervals. 'lbe normal automatic mode 6f valve operation (as provided for the condition of an accident) shall be employed to close the isolation valves priar to the perremmee {

of the leak _ detection tests.

All detectable lea'.s shall require repair and ntuto.

(3) All containment isolation valves, and check valves considered as necessary for containment but not included under (2) above, shall be tested at approximately yearly intervals, to verify the operability of 'thi'vai~ves. - b automatic dt;ntt ,ls and its instrumentation associated with these valves abati be tested at approximately Ytarterly intervale.

Defective operation shall require repair and nts ste.

.f g N 7

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

,....w....-~4 - ...., .,,--.+~ "-*"* - "-" - ** * * "'"""' '"* ' ~ ~^

p.. . .. _

' (b) An integrated leakage rats test shall te perfomed on the containment vessel within, three months of the issue date of the full tem operating license,1 i

and successively at intervals ta specified under

( 5 ), he taximum total leakiBe rate shall not exceed 0.2% in 2L hrs. of the contatued a.rospbert et a ;>rensuJe of 30 ps!g.

In order that integrated lenr.s representative of the "as is" conditjon t,e r.ite test t*

of the c ntairment, na prelir.inary mpantion of the led..ticht entidition of the conte. intent ba11df oc s hsil be performei which sill influe'ee the teru:.tr of the.cchedul<d integrated leaksge rate test.

CJost e cf the isola. tion vfdver t, hall be efectad by the no:- Al emans of the auttentic contrels pre.

vided for valve operatten.

leaks detected in th.e containment boajary or as a result of Isolation valve actfunctiou which j require repat ra te te made directly prior to the i test, or are ne:eauary to enable integra*.ei leaka6C rate testing to proceed, may be repaired provided such repairs are reported as' part c.T tbe record of the leakaCe rate results, i

E he integrated leakage rate test may be conducted in accordance with any one- of_ the following requiremente t ,

I (a) a sin l ps1E)gle test at 100% of design preosure (30

' (b) a single test at 33-1/3% of derisn-p ersun (10 pr$g)

The leakage rate detemined. frra this sing'e tes'. - ,

shall be corrected by the follevityt extrapolatim factor tc establish the leakage rate at the decip pressure leve] .

U Lt- = pPe2 . 1-g.1 , - y Le = $ Leakage rate at extrapolated design pressure - -

level Lt = % Wasured leakage rate- at teet air pressurt Fe"= f.xtrapolated prer.sure, atmosphere, sta.

Pt = Test fryssure, st ceptere sbr:

. . .; .:m. . . . . . . , . . . ~ ~ . - * = -v.-~~~~--~~ ~ ~ "~

.e e.e .een e , - ** ~ ~ ~=

31 -

(c) Three tents at prn- "m c orre r,p on d i rte, to E$5, 3$$, and $0% er de up prer.oure his aeries of testa shC 1 deter:Line (2 ) the ledare tchavior of the containment vessel es a functicn of test pressure,,and (2) the extrapelstion faster to te applied tr the reduced prer,oure tes' in establishing the

]ealace rate at desi n6p.-assure level .

The extrapola'iu factor, so deterrar*1, and af ter approval ty the Mvision cf Licensing *.rr$

hegulatien, may then be taed ':. conjun: tit n vitt future lotsage ra'e testa co-deted a t 33-1/31 f derign pressit .

The extrapolation factor as deterr.ined by thJ s series of three teste t'.C1 be ve:'.fiad at leas' once every tt trd contat::r.ent 2eedy9 rs'.e tent.

In the event this intervC of testing for verification of the extrapolation facters is less thar, five years, the verifice.tien testa may be e> tended to the next schedi ed leeJa6t rate tent.

The actual leakage rate as determined by either la).

(b) or (c) shall be corrected for the cent cir: ment conditions cf the air-steam mixture resulting frn.

the locs.cf-c oolant accido.t be :on ected lenkye rate shall not exceed the maxtcum e12csable ledere rate as specified under (k). In tha event the

\ m.uimum leakye rate is exceeded, a retest shall M made follevirg repairs of lenkr in the centa$w ent vesecl.

($) The frequency et leer. age rate testing of the or.'c r

• vessel ch*Lil not be less than once every five years except as modified by the opec *fied ect'edule if either of the following conditions occur:

(a) leaks are detected in the containmen'. vennel er isolation valve during trae tes '. vki:t - *q;J rc repairs to pemic continuation cf the tas:. b -

eause of excessive leakage.

(b) the maximu leakage rate has been exceeded as detemined, at any time, by the test results of (h) ab:ve

- " ;*  : -~ r g y .

l-

. -r d,

• ..g.,,,. ,t __

(' ,

Ac tion,,,,,,,,In f o rma tion _ Concurrence _Review DIVISION nF C0KPLIANCE Per Our Telecon File f Memo Route Slip Comument,,,,,,, Note 6 Return 1

Field RE: SAITON'S PROPOSED thK RATE TEST J. R. Sears - Region I

~ Saxton't r eposed leak rate procedure, dated Aprit 13, discusses on page 5 J. P. O'Reilly - hegion I I the relationship between their specified leak rate at design pressure and a leak rate based on their containment pressure H. L. Ernst - Region II decay curve. You might'be interested in knowing that laster and I are preparing H. D. Thornburg - Region III a proposal to DiNunno that is based on the same concept.

J. W. Flora - Region IV Their proposed use of the absolute method is surprising, especially since their permitted leak rate at 10 psig will be 0.13% based on their extrapolation model.

R. F. Sullivan - Region IV A temperature uncertainty of i l'F results in a leak rate uncertainty of i 0.2f. in E. O. Smith - Region IV the absolute method. Their use of an l imposed leak is certainly a step in the right diration. However, the scatter R. H. Engelken - Region V inherent in the absolute method will also be present during their imposed leak rate and may tend to complicate C. S. Spencer - Region V verification.

For couperison, their permitted leak rate R. T. Dodds - Region V based on the " conservative" flow model would be 0.087%, and on a laminar flow model would be 0.16%. Hor.eever, the A. 3. Johnson - Region V differences in extrapolation models are small compared to the uncertainties -

I inherent in the absolute method.

W. E. Vetter - Region V cc: L. Kornblith, Jr., C0tBQ j (

m B. H. Grier, CO RQ l

Cobb I Denton DATE: April 17, 1964 FR(Et Kornblith Grier Retturuth Nolan Long Wood

} h.-

.....g,...., -

- - - -' -- ' - - ~

~~ ~~ ~""T""OS '

a , . l. . s , .

l 4

9-he next scheduled leakage rate test shall then be conducted within an intenal not gesater than 12 acoths.

If the allovable leaksge rate,is not exceeded at the time of the one year intenal test, the testing intenal may be extended to three years.

If the allovable leakage rate is not exceeded at the time of the three year interval test, the successive leakage rato teste may again be erteidad to the five year interval, he accuracy of the les,ha6e rate measuring system in any test shall be verified by amerimposing a ecotrolled leakge rate (measured through a gas firw meter) upon the axisting vessel leakage rate, leslage rste. and coratinuius the test to measure the ecurpoe1+e 4

. _ _ ___._.______..____.__.m_ . _ . . _ . . _

9 ff hbe

[. {gjpkSN'h

'v DIVISION OF COMPLIANCE Action Information Concurre'nce Reviev k o: .

Memo Poute Slip ,

Coment Note & Retirn Per Our Ielecon File

.5 R. W. Kirkman

_ Regica I J. G. Davis Region II U: FAILURE OF D/P CEE-TRANS,11TTER AS A RESULT OF IN-LEAKAGE OF WATER VAPOR B. H. Crier The enclosed report, which discusses a unique Region III failure of D/P cell-transmitters, lack of l

[m ,

gaskets in vapor tight housings, is forwarded for information. The information should be D. I. Walker reviewed with ".icensees during the next routine

}

Region IV inspection.

Enclosure.

R. W. Smith Ltr, Saxton Nuclear Experi Region V ,

mental Ccrp. to Dr. P. A.

M:rrie , dtd 11/0i/68

_R. T. Carlson, 00: 1 N. C. Moseley, C0:1 F. J. Iong, CO:II i G. Fiorelli. CO III 1 H. b. Thornburg, CO:III J. W. Flora, CO:IV G. S. Spencer, 00:V I,

E012 L T

0'Reilly, CO:HQ 12/11/68 l

TROM: DATE-

_- _ _ _ - - - _ _ _ - _ - _ _ - _ _ _ _ _