ML20107E854
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UNITED STATES NUCLEAR REGULATORY COMM!$, N w ASHINCTCN. D. C. 20555 Docket No. 50-219 Jersey Central Power & Light Compan'y ATTN:
Mr. Joseph Ferraro, Jr.
Deputy Attorney Genatal Diviston of Law - Room 316 Newark, New Jersey 07102 Gentlemen:
OYSTER CREEK NUCLEAR GENERATING STATION 10 CFR Part 50, Appendix J, " Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors,' was published February 14, t-1973.
Since many nuclear plants had either received an operating license or their containments had reached' advanced stages of design or construction at that tice, some plants may not now be in full 3
compliance with the requirements of this regulation.
You are requested to determine if you are conducting containment leakage testing in full compliance with Appendix J.
'Ihis de termination ohould include the identification of any design features that do not permit conformance with its requirements or existing technical speci-fication requirements which are in conflict with Appendix J, (i.e.
less restrictive than).
It should be understood that while a containment
{
1eakage testing program may be in compliance with the technical speci-fications for your facility, the pro, gram may not be in conformance l
with Appendix J.
If you are not in full compliance, you should identify your planned actions and schedule to attain conformance to the Regulation.
Poss#51e
)
courses of action include design modifications, amendments to the technical specifications, and requests for exemption pursuant to 10 CFR Part 50, Section 50.12.
e i
Please submit the results of your study to us as soon as possible'but j
no later than 30 days from receipt of this letter, j
g of 1his request for generic information was approved by GAO undef a blanket. clearance number B-180225 (R0072); this clearance expires July 31!, 1977.
Sincerely, 3
(
~
Karl R. Coller, Assistant Director for Operating Reactors Division of Reactor Licensing
Enclosure:
Appendix J
- - = -
9604220117 960213
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Jsrssy Central Pcwar 6 Light Co..,
J AUG 1 yy cc:
G. F. Trowbridge, Esquire Shaw, Pittman, Potts, Trowbridge 6 Madden Barr Building 910 17th Street, N. W.
Washington, D. C.
20006 Jersey Central Power 6 Light Company ATTN:
Mr'.' Thomas M. Crimmins, Jr.
Safety and Licensing Manager CPU Service Corporation 260 Cherry Hill Road Parsippany, New Jersey 07054 Anthony Z. Roisman, Esquire i
Berlin, Roisman 6 Kessler 1712 N Street, N. W.
l Washington, D. C.
20036 Paul Rosenberg, Esquire i
Daniel Rappoport, Esquire 2323 S. Broad Street 1
Trenton, New Jersey 08610 i'
lionorable Joseph W. Ferraro, Jr.
~
Deputy Attorney General State of New Jersey i
101 Commerce Street - Room 208 i
Newark, New Jersey 07102
(
i Burtis W. llorner, Esquire j
Stryker, Tams and Dill 55 Madison Avenue Morristown, New Jersey 07960 George F. Kugler, Jr.
/
Attorney General State of New Jersey i
State House Annex I
Trenton, New Jersey 08625 Ocean County Library 15 Hooper Avenue Toms River, New Jersey 08753 i
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O N
I RULES AND RE7ULATIONS alon. De proposed
- rule would net have i
required the reporting of such triforma.
tion unless attempts to reduce the lew 8
age rate of poor leak tcht components
{4 failed to meet minimum leak tigntn%s acceptance criteria. Thus, components I
which required frequent adjustments or repair in order to meet allowable leak.
I age 11mits will be identmed and the spe-f effic reductions in leance rate values.
resulting from such ad;ustments, will be reported to the Commission. The identi-fication of such components will prodde the AEC with a sounder basis for judging g
whether or not containment leakMe s
rates could have been exceeded in the unlikely event a design casts accident were to occur. In adcation, such identi-Beation may provide insight into the fre.
This 10-Atomic Energy cuency and kinds of adjustmenta being made to components to meet the mini-CHAPTER l 4TOMIC ENERGY mum acceptable leakace limita and a
- COMMISSION basis for cather establishing a more fre-PART 50-.-UCENSING OF PRODUCTION quent containment leakage test schedule.
ANO UTluZATION FACILITIES or modifying or replacing cornponents.
~;
With regard to item (2) above, the Reacter containment Leaksne Testing for rule set forth below specifies criteria by Water Cooled Power Reactors which the licensee may for certain On August 27,1971.the Atomic Energ7 safety-related sy6tems temporartly dis-i ehmmiaaw: published in the PzDEaAL pense with drainage and venting to con-t Rsossrus (36 FR 17053) a proposed tainment atmosphere durmg Type A amendment to its regulations in 10 CFR containment leakare tests. The p oposed Part 60 which would specify the mint
- rule had speelfled that all systems wh:ch mum containment leakage test require-would connect directly with the contain-
- menta for water-cooled power reactors.
ment atmosphere and sould become ar.
Interested parties were invited to sub-ettent.lon of the contatnment boundary mit sTitten comments and suggestions should be vented to contaan=ent. S*.rtet for consideration in connection with the rompilance with this rule untJd nave re-propo6ed a. mend;nent althin 60 d&ys quired removing certaan safety related after publication in the FrosaAI, Rr,cis* systems from serMce fcr the duration of i
Tsa. Upon consideration of the comment.s the test and would hmtt the performance received, and other factors involved, the of the overall integrated contatnment ',
Commhaion has adopted the proposed leakage tests to these times when there amendment, sith certa!n modifications would be no fuel in the reactor, his i
in the form aat torth below, procedure is considered to be unneces-nignifwnt difference frorn the sarily conservative, amenAmmt published for comment are:
The inclusion of all safety-related sys.
(1) Modificauen of procedures govern-tems in the overall integrated contaan-ing containment inspection and leak de-ment leakage test can be accomplished taction surveys, as a prerequisite to con. While the reactor is fueled, and in a state !
ducting formal leakage testa, and clarift-of potentf al critteality, by mainte.ining i estion of the bcsis for reporting pretest the minimum number of safety-related j leakage values to the Cornmiuton. (2) systerns in an operable state until all
- estahMahment of criteria for daferring systems are tested Another option is to eartain safety-related systems from reg-periodically test the containment isola-ularly scheduled Type A containment tion valves in these safety-related sys-leakage testa (3) incorporation by refer-tems in accordance sith the rule set enee of the recently-issued American forth below. This would also assure that National Standard for leakage rate test-the requisite level of plant safety will be kig of containment structures for nuclear provided during the containment leak-reactors into the regulation, (4) inclu-age test program without compromising alon of nitrogen gsa ns.s su'. table testing the requirements for including EIl sys-medium for testing the lenktightness of tems which penetrate the containment stiven, and (5) inclusion of water-leak-boundary in the leakage test.
ass test and acceptance criteria for con-The proposed r' ale required the use of tainment isolation valves which are test methods descMbed in proposed sealed against containment atmosphere American Nuclear Society Standard ANS j
ouusakage during a dea!gn beats accident 7.60 by referenemg a portion of the pro-i eendition by means of a seal water sys-posed standard. On March 16,1972, the j tem. In addition, ed14ctlal and format American National Standards Institute ebanges were made, approved ANS 7.60 and ot5clally issued Wit.h regard to item (1) above, the it for use as ANSI N45A-1972. Amedean
- rule set forth below requires the 11censee National Standard. "Isakage Rate Test.
4 te Iduntify specifically those componenta ing of Containment Structures for Nu-
, whose initial poor leak tightness per-clear Reactors." The standard has been l
- formance precluded completion of a reviewed for compatibility with the pro.
! Type A containment leakage test and to posed rule and is was concluded that in.
report this information to the Commas-corporation of the requirements of ANSI pggenAL testsfen, Vol. Se, NO. 34-WSONGSDAY, NesuAsy 14,19r3
-d h
k, 4386 RULES AND RE2ULATICNS
)
N45.4-It71 b'y ref rence wruld enhance mintmum requirements for periodic v:ri-D. "C2ntainment teolation velve" mians the quality of containtnent leak testing. fleation by tests of the leak. tight integ. any vcve which to retted upon to perform a
- "'*3.*im
"' '*oiatt n function.
,[.'g[*,'$' g"3,p, g("M*",*8 Accordingly, the rule set forth below now rity of the primary reactor containment
~
Specifles that the Type A containment and associated systems for water. cooled ot r leakage testa shall be conducted in ac-power reactors, and the acceptance crl* Trpe B. and Type c teena. described in It F.
cordance with the provisions of AN8I teria for such tests.
n.o. and u.H. respectively.
N46.4-1972.
Pursuant to the AtoGic Energy Act of D. "Imaanse rate" for tant purposes is that The proposed rule limited the leakage 1954, as amended, and sections 552 and lestaeo which occurs in a unit of time,ataad testing medium for reactor cor.tainment 653 of title 5 of the United States Code, u a percentage or wetant of the orarlas con.
Asolauon valves to air, which is wide 17 the following amendment to Title 10,
- "*"#***'3""*L'""'h'l'***8"
teet pressure that escapes to the outside used in the containment leakage testing am !.
e ral a
na, atnwhm ounng s abhour test pertod.
program. However the une of nitrogen gas for valve leakage testang is also tech. Part 50, is published as a document sub.
E. *Ovmil integrated leakage rate" means nically satisf actory. Accordingly, the rule ject to cod 1Scation to be effective on that leakage rate which obtains from a aun2 mation or leakage through all potential leak.
set forth below specifies that either air March 16,1973.
ase pathe including containment m e:ds, or nitrosen may be used as the testing
- 1. A new paragraph (o) is added to
'alves. attinsa, and componenta ahich pene-
' spedium in the conduct of the valve leak-I 50.54 to read as follows *-
*"'*1"'"*"'-
age tests.
F. " Type A Testa" means testa latended to The rule set forth below expands upon 6 50.54 Condillone of licenm.
measure the primary neetoe ccatainment
- '3 3 3 " *' 8'd 3 '* " '8' ( 3 ) "" ti
- the requirement contained in the pro-
+
e e
+
+
containment has been completed and ts ready posed rule for testing valves, sealed Mth (o) Primuy reactor containments for for operation, and (2) at periodie interva;s water from a seal. water system, by in-water cooled power reactors shall be sub-therearter.
cluding minimum water test pressure ject to the. requirements set forth in
- o. "Twe s Testa means tuta intended to and test acceptance criteria.
Appendix J.
detect local leaks and to sneasure leakage ne proposed rule required that the across each pressure.containing or leakage.
valves be subjected to a seal-water sys.
- 2. A new Appendix J to added to read timating boundary for the ro:tostar primary as follows:
i reactor contstamnt penetrations:
tem operablitty test to establish that Anasma J
- 1. catammnt pmtrations whow desyn the valves could be satisfactortly pres.
$p'P g peneNtio$ n'td' d 'N.*
aurir.ed with seal. water. 'Itere was no rarmaar asseton cowrarwwsar Lanuos raar.
on p t
i requirement to rneasure the rate at which two ros ** Tom. coot.no rows manctoaa panaton Mows. and electrical penetrations 1
water leaked past the valve. It had been
- 1. Introduction.
Atted with Seatble metat seeJ aamernbtles.
l assumed that the Seal. water inventory II. Explanation of terms.
- 2. Attlock door sea's. Including door operat.
would be adequate to seal the valves nL tastap test requstements.
ing mechanism penetrations which an part i
against outjeakage of containment A. Type A test.
or the containment pressure boundary, atmosphere during the design basis acci.
8 TrP* 8 t"t.
- 8. Do es with resuient secs or gastets ex.
I dent condition. However* the lack of a C D' C *****
- P ' ' ' "'3 * * 'I d*d d"'* -
D. Portodic retest schedule.
- 4. Components other than those Itsted in cpeelfic water inventory criterion against IV, spectat tast requirements.
II.O.2. n.o.2. or n.o a which must meet t.be which actual valve leakage rates would A. contatament modiscattors acceptance criterta in In.n s.
i p
be measured, could result in an inade-B. Multiple leakage-barrier containment 4.
H. '*rype c Testa" means testa intended to i
quate supply of sul c4 tor fcr valve V. Zuspectioa and repcrting of testa.
nessure contatament teolation valve leatage sealing with attendant losa of v.he con.
A. Containment inspection.
rates. The containment isolation vaJves in.
tainment isolation function. Accord-B. R* Port of test rnulta.
oluded are those that:
Ida a direct c ects between the ingly, a provialon has been incorporated
- 1. Im" 1"' d' ""d " d ' * **" PD "" *# 'A ' P "
- into the rule set forth below which it.
quires that the valve leakage rate shalj one of the conditions of an operating mary reactor containment under normal op.
not exceed the seal. water inventory, on lloeraes for ester. cooled power reactore as eretton, such as purge and ven tila tion, i
specteed in 6 60 64(c) is that primary r,.
vacuum relief.and tnstrument valves:
the assumption that the scal water sys" actor containment 4 shMJ meet the contain.
- 2. Are required to close automatically upon i
tem will be pressurized for 30 days at ment testage test requirementa est forth Mc* pt of a containmot indatte signal in 110 percent of the calculated peak con. In this appendtx. These teet requirementa respese to controte intended to efect con.
j tainment internal pressure related to provide for preoperational and periodje vert. tatamos taoistion:
1 the dealgu basis accident. With the in, ccatta by tests of the leak. tight integrity
- 3. Are required to operate totermittently clusjon of this requirement, the require, of the primary reactor containment. and sys, under postaccident conditions; and anents for conducting only a seal. water tems ar.d componenta which penetrate con.
- 4. Are in main steam and feedwater ptptng i
tainment of water-cooled power reactore, and other systems which penetrate contain.
system operability test were eliminated. and estabitah the acceptance criterta for ment of direct cycle boutng water powes Containment is provided for water
- such testa. ne purposes of the testa are to reactore cooled power reactors to prevent un-aneure that (a) leaksee through the prt.
I. Pa (pa i r ) means the ca:culated peak controlled releases of radioactive ma. mary reactor contatr. ment and systems and containment internaJ pressure reisted to the terials to the environment !! the componente penetrating primary contatn. destan bants scendent and spectaed either in barriers provided by the fuel cladding sment shall not neeed clowsbte teskase rate the teeboscal spectacation or sesociated beaes.
and reactor coolant pressure boundary s:ues as specta d in the technical specs.
J. Pt (pa.t s ) means the containment should be breached. Testing the reactor.'cesttaa or un cated bases and m) penodie
,,duced teet pressure selected to mens.
containment for leakage helps to assure E,*a,"$d isot$aoY,#s res la [rformed E M 'a't N I"*8' '* '"""8 P**
- that, ao that proper matatenance and repatre are u
(a) hakage of the primary reactor made during the service life of the contain*
rou au a I
g ste r a containment and associated systems is snent, and aretems and component 4 pene* as spectfted for preoperational testa La the held within allowable leakage rate limits trating primary containment. n oe. test techniemi spectacations or u.actated bases as specifled in the technical speciacations requirements may also be used for su"*
and na spectaed for periodic testa in the opl in estabitahing appropriate containment or sasociated bases of the license; eroting license, teakage test requirementa to technical spect.
(b) Periodic surveillance is performed aestions or associated bases for other types L Ld (percent /24 hours) means the de.
to assure proper matutenance and leak of nuetear power reactcre.
sign leakage rate at pressure. Pa. as speciced repair during the life of the contain, in the techntent specineations or associated U 88P88N8' Tmas bu s.
menti and (c) De containment will continue to A. " Primary reactor containment" means M. Lt (percent /24 hours) means the mast.
perform its function throughout the life the structure or veseel that encjosas the com. mum allowable leakage rate at preasure Pt Of the plant.
Ponenta of the reactor codant pressun derived from the preoperational test data boundary, as deaned in i 60.2(e), and serves as spect8ed in IU.A.4.(a)(ut).
He amendment whteh follon pro. as an eenentinur leak ttsht barrier against the M. Imn. Ltm (percent /24 houn) means Vides Uniform requirements for contain. uncontrolled retsase of radaoactivity to the the total measured containment leakage rates ment, leakage testing. It specifles the enetromment at pressure Pa and Pt. respectively, obtained NDetAt M0tStM Vot. 30, 000. 36-WIDN450AY, MaaWARY 14,19y3 i
RULES NO RE!ULAfl0N5
)
Oti7 froen 't'esting the coltainment with compo. tema sha!! bo Crained cf witer.tr other Sunds (b) Arceyfinca evifJrfe-(t ) Redkred Dente End systems in the state se close as to the catant necessary to assure exposure of preseure fests. De leakate rate Ltm sba;l be practical to that which would estet under the erstem contatnment laolatloc valves to less than 0.73 Lt If local leakage rneaaure.
destas baala accident condtttons (e g Tented, containment att test preneure and tc easure enents are taken to effect repaJrs in order to dretned, flooded or pressurtzed),
they will be subjected to the poet. accident meet the acceptance critetta, these messare.
- i O. " Acceptance ersteria" means the stand. diferential preneure. Bretems that are ee. menta shM1 be taken at a test pressun Pt.
and agannot which tent results are to be quared to maintain the plant in a eafe cone (2) Peas pressure teste shall be conducted essepared for estabitahing the functional ac. dation during the test shall be operable in lam shall be !ces than 0.78 La.11 loca11ema.
septabutty of the containment se a leakage their normM mode, and need not be vented. age measurernente are taken to afect tvWs insalting boundary.
Bretoma that are normauy filied with water-In order to meet the sceeptance cr.ter.4, BI. Laamass TasTwo Raetnaststarte an4 operatW tander poet secht condt. these measummenta shan W tam at a w tions, such as the containment heat removal pressure Pa.
A program constating of a schedule for con. system, need not be vented. However, the
- 6. Addassonal Requirements. (al if any ducung Type A. B. and C tests shall be de.
contMnment toolation valees in the systema periodic Type A test falls to meet the app.
eeloped for leak testing the primsry reactor deSned in IIIA1.(d) ebau be tested in ac. cable acceptance criteria in HIh(bl. tie containment and related systeme and compo. cord = + with III.C. The measured 1*akage test schedule appitcable to subsequent Type acata penetrating primary containinent pres. rate from these teste shall be reported to the A tests wiu be revaewed and approved bf the sure boundary.
Coenmienton.
Commianlon.
Upon completion of construction of the
- 3. Conduct of fests Prooperational leakage (b) If two consecutive periodic Type A
)
primary reactor entainment, includine in.
F*** 8**te at either reduced or at peak pree. *ests fati to meet the oppiscable neceptance 3
stallation of all portionm of mechanical, Suld. sure, shall be conducted at the intervMs criteria in IIIA&(b). notetths*.anding the
)
eisetrient. sad instrumentation systema pene, spec 1 Sed an HIA perWlac retest ehedute of IILD. & Type A testing the primary reactor containment
- 3. TcJf methods. (a) All Type A testa shall test shall be performed at each plant shut.
pressure boundary, and prior to my reactor be conducted in accordance with the prowl
- down for refueling or approaluately every operating period. preoperational ar.d pertodle alona of the American Natnonal Standard 18 months, thichever occurs Srst, untti to o i
leakage rate testa. as appincable. shall be N46 bl972. IAskage Hate Wsung of Con
- consecuuu Type A testeInnt the acceptance 3
conducted in accordance with the follnytng: taltunent Structures for Nuclear Reactors. criteria in IIIA6(b). mfter which time the Afarch 18 1972.8 The metuod chosen for th*
retest schedule spectaed in III.D. may be A. firpe A test-1. Pretest requirements, (a) Containment inspection in accordance initial test shall norinauy be used for the resumed.
with V.A. shall be performed as a prerequistte periodic teste.
D. Type 8 fests.
- (b) The accuracy of any Type A test sha!!
- 3. Test methods. Acceptable means of per.
be verLSed by a supplemental test. An accept, forming a preoperational and peLadic T)pe to riod the 1 ation th n
tainment inspection and the performance of able mmod la dwM in Appene C M B W IMW
)
the Type A test no repatre or adjustmente ANSI N4A4-1972. The supplemental test (a) EastnLnation by he'.de leak. detection shall be made so that the containment can meth d eclected sha!! be conducted for suin. method (or by other e".atvalect test rnethods be tooted in as close to the *as is" condition cient duration to establish accurately the euch na mass spec".ometerl of a test cham.
as practical. During the period betwaen the change in leakage rate between the Type A ber, prneurW sith air, nitmm. or pneu.
3 ocenpletion of one Type A test and the initta. and suppWmmal test. Resulta imm this mauc Su!G epecLSed in ne technical 4
tion of the containment inspection for the 8uPplemental test an acceptable provided spec 1Scations or associated bases and con.
subsequent Type A test. repatre or adjust. the diference between the suppleroental test structed as part of individual containment spente chau be made to componenta whose data and the Type A test data le eithin 0.25 P8ne trations.
leakage exceeds that spec 1 Sed in the techntral y ( r 023 Lt). If results am not within 025 epectSestion na soon as practical after iden. La ( r 0.26 Lt), the umaon shM1 be deter *
(b) Measurement of the rate of pressure tlacation. If durtr.g a Type A test. Inclutung Intned, emmttre act:on takm, and a suc. loss of the test chatnber of the containmer.t the supplemental test specified in IHAS-(b). emful supplernentM test perfortned, penetration preasurtred with Mr. Litrogen, or pneumatto Sund spectSed in the technical j
potentially esnssive leakage paths are iden.
(c) Test leakage rates aball te calculated spectScattoLa or associated bases.
118ed which will interfere with satisfactorf using absolute values corrected for instru*
1 (c) Imakage surve!!!ance by means of a l
completion of the test, or which result in the met ow*
permanently installed erstem with provisions t
Type A test r)ot meeting the acceptance erg. ' 4. Preoperational leakape rate fes:e. (a) for continuous or intermittent pressurization
)
teria yII A.4.(b) or III AS (b) the Type A test Test pressure-(1) Jteduced pressure fests. of indleidual or groups of containment pene.
i
(
aball be terminated and the lestage through (t) An inattal test shaji be performet at a trattoru and measurement of rate of pres.
such pathe shall be measured using local pressure Pt. not less than 040 Pa to a maure sure lose of air, alttogen, or pneumatic Su.d 1
leakage testing rne.boda. Repairs and/or a leakage rate Ltm.
specLSed in the technical spec 1Acation or adjustmenta to equipment shall be made and (11) A accond test shall be performed at anaociated bases through the leak paths.
j a Type A test performed he corrective ac. pressure Pa to measure a leakage rate lanL
- 2. Test Pressure. All preoperettonal and ston taken and the change in teamage rate (tu) ne leakage enaracteristica yalded periodic Type B teets shall be performed er determined from the testa and cverall Inte. by measurementa Ltm and Lam shall estab. local pneumatic prehsurtzat*on of the con.
1 grated leakage determtced from the local lost 11sb the mastmum allomable test leakage tatament penetrations. ettber individually or and Type A testa aball be included in the rate Lt of not more than La (Ltm/ Lam). In in gtoups, at a preasure not less than Pa.
3 report submitted to the Cornmlaston as spe. the event Ltm/1Am la greater than 0.7. Lt
- 3. Accepgance enteru. (See also Type C c18ed in Y.B.
shall be spec 18ed as equal to h (Pt/Pa):e. testa.) (a) The combined leakage rate of all (b) Closure of contalnment teolation valves (2) Peak prsrure fests. A test shall be per. penetrations and valves subjecs to Type B i
for the Type A test shall be scoomplir. bed by forme 1 at pressure Pa to measure the leakage and C testa shall be less than 0 60 La. with mormal operation and without any preltml. rate !am.
the esceptica of the valsee spectSed in mary emerclatng or adjustmenta (e g..
no (b) Acceptance crtterte.-( t ) Jteduced III.C.2.
tighteatng of valve after closure by valve pressure tests. The lea 4 age rate Lt.m abau be (b) Imakage measurernents obtained motoe). Rellaire of matoperating or leaking lone than 0.76 Lt.
through component leakage surveillance sys.
valves shall be made as necessary. fr. forma
- i tion on any valve closure analfunction et (2) Psa4 pressure fests. De leakage rate tema te4 continuous prea.urtzstion of in.
j entve leakage that requttee corrective action Lam shall be lees than 0.76 La and not greater d tvidual containment componenta) that 1.han L4.
befeet the test. shall be included in the re*
matntains a pressure not less than Pa at in.
i aubmitted to the Commianton as spect.
8.Ptnodle leakepe rete festi-(t) Test pres. dividual teet chambers of containment pene.
I eure. (1) Reduced pressure teste shall be trations during nortnal reactor operstaon, j
in V.5-conducted at Pt. l are acceptable in Inou of Type B testa.
(e) %e containment test condillona aba!!
stabillse for a pertod et about 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior, at Pa.(2) Peak pressure testa shall be conducted C. Test C rests.
to the start of a leakage rate test.
- 1. Test smethod. Type C testa shall be per.
(d) %one portions of the fluid systems formed by local pressurization. De pressure shall be applied in the earne direction as that are part of the reactor coolant preasure ANSI N46 4-1972 Leakage Rate Testing of that when the value would be required to 1
boundary and are open directly to the con. Containment 8tructures for Nuclear Steactora perform its safety function, unless it can talament stanosphere under poet. accident (dated Mar. 16. 1972). Copies may be ob.
De determined that the resulta from the tests sonditions and become an estenaton of the tained from the American Nuetear Society, for a pressure applied in a different direction boundary of the containtnent shall he opeced 244 East Ogden Avenue. Hinsdale. IL 60821. wn!! provide equivalent or more conservative er vented to the containmerrt atmosphere A copy is available for inspection at the results. De test methods in IILB 1 may be petar to and during the test. Porttona of Commtaston's Pub 11C Document Room.1717 substituted where appropriate. Each veJve to elemed erstems laalde contaJament that pone.
teste contalassant and rgture as a result of X Otreet NW., Washington. DC. The incor. be tested shaal be closed by normal opera.
a loss of coolant accident shall be vented to puention by reference was approved by the Lion and without any prel!minary esercastng Direewr of the Federal Register on Octo.
the containment atmosphere. All vented eye. ber 30,1972.
or adjustments (e g., no tightening of valve after closure by valve motor).
ftOSGAL teellfEt, YOL 38. 8e0. 36 -WEONfS0AY, pattUAty 14,1973
~
d t
~
b*
'es autas AND REGULATIONS e.
' S, feet' pressure. ( ) Valves.' walene pres. ~ ge aste meets the requiremeu of th3 ao.
a g
eartsed with Sund (e g, water, altsugen) peadas. Other eoructures of multiple barrter Speau a enel ersteen, aball be pressurtmed with or subatmospheru sor.tainmente to g., eso.
9 mar er altregon at a pressare of Pa.
andary containemones for boutng water reac.
(b) Valves, which av ersted with Suld tore and akteld butidange for pressertuod frota a esal eyetem shall be pressurised with weser reactore that encloes the entist prianary that Sund to a promeure aos toes than 1.30 Pa. remeter containment et poruor.e thereof) g-8 Afeepteate artierten. 'line combined shall be subject to Ladstidual teau in aseerd.
. ledage sete for att penettstlene and valves
- snee with the precediares apostand la the i
enhjort to Type 3 and C teste aban be less - techsteal spec 1Asmusena, or a-maw bases. -
f then eAs La. Imetase from eenteinment A' #**#*'****8 8**P**"***
- 8***'*1 1**
nas:staen e lees that are aged mth aute frise a emel eyotem easy be escluded when. Y. heerecT1ogr atro Roroevnse or Teere deternettley the cornbtned leakage rote r spection of the accessible laterior and este.
Prereded,That; rior surfaces of the ecstainment structures g
~ (a) Seeb va19ee have been comonstrated and componente aball be performed prior to to have Suld leakage retee that do not es. any Type A test to uncover may eftdence of esed those spec 18ed in the techsleal apocl. structural deteriorsuon which may afect Seatione er associated bases, and either the sentaineneet striactural Lategrity (b) The Installed teatation valve seal,, of leak ttghtness. If there le erldence of water efttem Ruhl Intentary to eusictorrt to structural deteriorsuon. Type A teste shal!
secure the sealtag funotion for at least 30 not be performed unt!! corrective action te este at a preusre et 1.10 Pa.
taken in accortinnee with repatr procedurse.
D. Periodde Petest sc%edule 1.
Type A meadestructive enastantions, and teste na Geef. (a) After the preoperstlanal leakage sport 8ed in the applicable code spectSed in -
rate teste. a set of three Type A teste than be i 60 06a at trae oceamencement of repau west such structurni detertorstion and cor.
performed, et apprastautely equal laterva:e during each 10 year servtco pertod. ne thtre reelte actione taken ohn!! be sported as test of each set shan be conducted when the part of the test Mport, subenittee in acces41. -
ance with V.B.
plant la shutdown for the 30-year plant in, sorrice inspectione.e
- 3. Aeport of test results.1. The preopers.
(b) Permissible perlede for testing. The tional and pertodic teste shall be the subject pttformance of Type A teste shall be limited of a summary techtucal report submitted to to periode when the plant fact;nty le non. the Commiasion approximately 3 montba operational and secured in the shutdown after the conduct of each teet. The report condition Under the admintstrattre control shall be titled " Reactor Containment Sulld.
. and in secordence with the safety procedures tog Integretod isak tunte *14st."
~
deoned in the lleenee.
- 3. ~The report on tbo preoperational test
- 2. Fype # teste. Type B teste encept testa sha!1 Include a echamatte arrangement of the fbr air locks that! be performed during each leakage rate measurement system, the in.
reactor shutdown for refueling, or other cou. strumentation used the suppismental test ventest interva3. but in no case at Interf ale rnethod, and the test program selected as sp.
gvester than 2 years. Air 1Ms shan b+ imod pitcable to the preoperational teet, and all at 6 month intervals. Ptowever, air lor.ke subsequent periodle testa. The repo.1 shall l
which are opened during such intettale.*shall contain an analyste and interpretation of the be tested after each opening. For primary leakage rate test data for the Type A test 3%ctor containment penetraticas employtog results to the estent necessary to demon.
a =ma=eur lottavo amenatwing system, atrate the acceptability of the containment's
- may, notwithstanding Gm. seet schaduw spee. ersteria.
eptane.
Typ.
easte. eene,t ser us of at, wene, waad.
,si.
m m.eung the 18ed under m.D.I be performed every other
- 3. Por each periodle test. leakage test re.
I reseter ehwndown for terueltog but in no came sulte from Type A. B. and C teste shall be re.
1 at latervale greater than 3 years.
ported. The report shall contein an analyule y
- 8. Type C rests. Type C teste shall be per. and interpretation of the Type A test resulte
- formed during each reactor shutdoorn for re. and a summary analyste of periodio Type B feeling but in no case at intervale greater and Type O teste that were performed since than 3 years.
thq 3ast Type A test.14akage test resuWe j
front Type A. 3. and O teste that failed to IV. Seussa Tasseees flmesensueeerse A. Centstement mWijteettom. Any unajor M.BJ and m'.CJ. roepectively, aba!! he se.'
moeneatton, replacement of a component ported in a esparate accompanytag outnanary walets to part of the primary reactor con. report that includes an smalyste and later.
talnasent boundary, or reaealing a esti.
welded door, performed af ter the preopera, pretation of the test data, the least.equares tional leakade rate test aball be followed by 84 analyste of the test data, the instrumenta.
either a Type A. Type B, or Type C test, as iten error analysts. and the structural condt.
appliemble for the area seected by the modl. tiona of the contalament or componente. Af Settlon. The measured leakage from thle test any, which contributed to the fatture in 1
shall be included A the report to the Cum. meeting the acceptance criteria, lleeutta and J'
asleston. required by V.A. *fhe acceptance crl* analysee of the supplemental verttScation terla et MA8.(bl. m S 3 or m.CJ as test employed to demonstrate the va!!dity of appropriate. shall be met. 3dinor modtSca. the heage rate test measuremente shan also t&one, replacemente, hr reneallag of seal
- be includd.
)
(
welded doore, performed directly prier to the
,,g,,4 esaduet of a seheduled Type A teel do not 948. 954, as amended! 43 US.C. 3133. 3134 recluste a seperste test.
3901{1), Itses)
- 3. Multiple 8eshape barrier er substmee.. Dated a4 Oersnantown. Md., Ms Mh pherte senfassmente. The prianary reactor contalarment barrter of a multtple barTter or day of Pettynary 1973.
substmospherte eentalament ahnu be sub.
g g u m,y,, u.a, Jeeted to Type A taste te verity that ste leaa.
1 1
Patri. C. Bawnsa.
Asergidt of thd Commisedom.
eauch taseretse hopecuena are muw by I seJea.
IPm Dee3surres Pted MS-Ts;sles aan) fBSE WSISTER. VOL, 3e, NO. Sb we0NESSAY, PIB8UARY 14 M3 i
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