ML19326B962
| ML19326B962 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/05/1975 |
| From: | Goller K Office of Nuclear Reactor Regulation |
| To: | Phillips J ARKANSAS POWER & LIGHT CO. |
| Shared Package | |
| ML19326B964 | List: |
| References | |
| NUDOCS 8004180669 | |
| Download: ML19326B962 (2) | |
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AUG 051975 a --
7.eket No. 50-313
-DISTRIBUTION fr:. ~.
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Arkanses rover & Light Company Local PDR MBFairtile ifh:....
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nr. J. D, Thillits.
ORB #2 Reading DEis
{Ds,enhut3gg M Senior Vice President KRG011er i
Production, Transeission TJCarter
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and Engineeriuy DLZiemann 3,7.g;.
Sixth and Pine Streets h'Econverse
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[.). ski-10 CFE Part 50, Appendix J.
Frinary Reactor Containeent Leakage f
Testing f or kater-Cooled Power Ecactors," vas published February 14
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1973.
Since ncny nuclear plants had either received an operating license or their containments had reached advanced stares of design F
or const ruct ion at that t ire, sone plants nay not nov be in full h
f..=;t cerpliance with the requircr ents of this regulation.
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You are requested to deterrine if you are conducting containcent I:l:
leakare testieg in full compliance with Appendix J.
This deternination E
should include the identification at cny deripn features thet do not t
perrit conformance with its recuire= cots or existing, technical sp ci-l""
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ficat ion ree;uirenents which ere in conflict with Aprendix J. (i.e.
less restrictive than).
It should be understood that while a contcinrent leaknee test int progren coy be in compliance with the technical speci-fications for your tacilit y, tbc pro: ran cay not 1,c in conforr ence eit h.t riendix J.
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cet ions end schtdule to attain contormance to the 1:erulation.
Poscible Wr:s If you are not in full conpliance, you should ident ify your planned courses at setion include des irc.odi fications, crendr.:ents to the technicel Ei-sceci fiest ions, and requests f cr exemption pursuant to 1 0 C rit Part 50, Lect ion 30.12.
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ricese subnit the rea, ult s of your st uc y to us as soon as possibic but no tol er than 30 dcys f roe rece ipt of t'ils letter.
This re r,te s t for rent'ric ir.forcation t:as approved by C/0 under a
'L blanket clenrance cunber E-lbO225 (Ti072); this cicarance expires
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July 31, 1977.
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l Sincerely, r.
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- Original si.tned by R. A. Purple T E T I I. Co l I t' r. s' it M i f, t r ai l EirfJter
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Arkansas Power & Light Company AUG 0 51975.
ec w/ enclosure:
Horace Jewell House Holms & Jewell 1550 Tower Building Little Reck, Arkansas 72201 Mr. William Cavanaugh, III Production Department Post Of fice Box 551 Little Rock, Arkansas 72203 Arkansas Polytechnic College
- Russellville, Arkansas 72801 l
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RULES AND RE!ULATIONS 4E sion. The proposed rule would not have required the reporting of such informa.
tion unless attempts to reduce the leak-age rate of poor lenk-tight components failed to meet minimutn leak-tightness acceptance criteria. Thus, components which required frequent adjustments or repair in order to meet allowable leak.
age 11mits will be identified and the spe-cific reductions in leakage rate values, resulting from such adjustments, will be reported to the Commission. The identi-Scation of such components will provide the AEC with a sounder basis for judging whether or not containment leakage
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rates could have been exceeded in the unlikely event a design basis accident were to occur. In addition. such identi-Scation may provide insight into the fre-Title 20-Atomic Energy quency and kinds of adjustments being made to components to meet the mini.
CHAMM EM mum acceptable leakage limits and a basis for either establishing a more fre-PART 50-UCENSING OF PitODUCTION quent containment leakage test schedule.
AND UTluZATION FACIUTIES or modifying or replacing components.
fleector Containment Laaksge Mg h With regard to item (2) above, the E***' "
rule set forth below specifies criteria by which the licensee may fo* certain On Atagust 27,1971, the Atomic Energy safety-related systems ternporarily dis-rin-meanton pubilshed 'n the Froamar. pense with drainage and venting to con-Roonsraa (36 FR 17053) a proposed tainm,nt atmosphere during Type A amendment to its regulations in 10 CFR containment leakage tests. The proposed Part SO which would specify the mini-rule had spec! Sed that all systems which mum contahsmant leakage test nouin-would co'mect directly with the contain-mants for water-cooled power reactors.
ment atmosphere and would become an Interested parties were invited to sub-extension of the containment boundary mit written comments and suggestions should be vented to containment. Strict for considerstics in connection with the compIlance with this rule would have re-proposed==andment within 80 days quired removing certain safety-related after imhlte.esan in the Psammar, Ruors. systems from service for the duration of Tsa. Upon consideration of the aamments the test and would limit the perfonnance received, and other factors involved, the of the overall integrated containment r*ammt== tan has adopted the proposed leakage tests to those times when there amendment, with certain modiacations would be no fuel in the reactor, This an the form set forth below.
procedure, is considered to be unneces-m n manne diferencan from the sarily conservative.
s amandedet imhit=had for cr mment are:
The inclusion of all safety-related sys-(1) wadina=*8a= of procedures govern-tems in the overall integrated contain-2ng een ann-me inspection and leak de-ment leakage test can be accomplished e
taction surveys, as a prerequisite to con-while the reactor is fueled, and in a state ducting formal leakage tests, and clariS-of potential criticality, by maintaining ention of the basis for reporting pretest the m:nfmum number of safety-related lenkese values to the Cammi== tan (2) systems in an operable state until a!!
es nhat.hmane of criteria for deferring systems are tested. Another option is to e
certain safety-related systems from res-periodies11y test the containment Isols-usarly mehadniad Type A containment tion valves in these safety-related sys-Isakage tests. (3) incorporatten by refer-tems in mocordance with the rule set once of the recently-issued American forth below. ' Ibis would also assure that National Standard for leakage rate test-the requisite level of plant safety will be kig of contalmn=nt structures for nuclear provided during the containment leak.
reacters into the regulation. (4) inclu-age test progrpm without woww-using alon of nitrogen gas as.a suitable testing the requirements for including all sys-medin== for testing the lenktightness of tems which penetrate the containment valves, and (5) inclusion of water-leak-boundary in the leakage test, age test and acceptance criteria for con-The proposed rule required the use of tainment isolation valves which are test methods described in proposed sealed against containment atmosphere American Nuclear Society Standard ANS outleakage during a design basis accident 7.60 by referencing a portion of the pro-condition by means of a seal-water sys-posed standard. On March 16,1972,the tem. In add! tion, editorial and format American National Standards Institute changes were made.
approved ANS 7.60 and of5cially issued With regard to itern (1) above, the it for use as ANSI N45.4-1972, American rule set forth below requires the licensee National Standard, " Leakage Rate Test-to identify spec 1Scally those components ing of Containment Structures for Nu-whose initial poor lesk-tightness per-clear Reactors." The standard has been formene= precluded completion of a reviewed for compatibility with the pro-8 Type A cantainment leakage test and to posed rule and it was concluded that in.
report this information to the Commis-corporation of the requirements of ANSI FEDERAt MSISTER, VOL. Se, NO. So-WEONE50AY, PEaRUARY 14, 1973 l
4 86632Sb797
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s RULES AND REGULATIONS 4%7 e
from testing the containment with compo. tems shall be dralned of witer or other Sunds (b) Acceptance critetta-(I) Jteduced nonta and systema in the state as close as to the estant necennary to maeure exposure of pressure tests. The leakage rate Ltm shall be practical to that which would estat under the system containment isolation valves to less than 0.75 Lt. If local leakage measure.
design baats accident condluono (o g., vented, containment air test pressure and to amoure Dwnts are taken to effect repaire in order to dratned, flooded of pressurtsed).
they will be subjected to the poet. accident meet the acceptance criteria. these measure.
O. Acceptance criterta" means the stand. digerential pressure. Systems that are re. ments sha!! be taken at a test pressure Pt.
ard agalort which test reeutta are to be quired to maintain the plant in a safe con.
(2) Pesk pressure tseta shall be conducted compared for estabitshing the functionsJ ac.
dition during the test shall be operable in Lam shall be less than 0.75 La. If local tees.
ceptability of the containment as a leakage their normal mode, and need not be vented. age measurements are taken to a3eet repaws limiting boundary.
Systesne that are normany Slied with water-in order to meet the neceptance criteria, IIL f unas 7tet!Me Rsemaanssarve and operating under post-accident cond!. these measurements sha!! be taken at a test ttona, auch as the containment heat removat pressure Pa.
A program conatsting of a schedule for con. erstem, need not be vented. However, the
- 6. Addutonal Requirements. (a) If any ducting Type A, B. and C teats shall be de.
containment isolation valves in the systems periodio Type A test falla to meet the appin.
veloped for leak testing the primsry reactor deaned in III.A.1.(d) shall be tested in ac. cable acceptance criteria in m.AA.(b). the containment and related systems and canpo. cordance with m.C. De measured leakage test schedule applicable to subsequent Type nonta penetraung primary containmot pree, rate from these testa shall be reported to the A testa wiu be reviewed and approved Dy the sure boundary.
Coenslaston.
Commisalon.
Upon completion of construttlon of Obe
- 2. Conduct o/ tests. Preoperationa11eakage (b) If two consecutive periodic Type A primary reactor conta1 ament including th.
rate teste at either reduced or at peak pree-testa fan to meet the appitcable acceptance stallation of a!! portions of mechanical, fluid sure, shall be conducted at the latervals criteria in IIIAA(b). notwithstanding the eteetrical, and instrumentation systema pene.' 'P*ctaed in In.D.
periodic retest schedule of mm., a Type A trating the primary reactnr containment
- 3. Test methods. (a) AU Type A toets shall test shall be performed at each plant shut.
prosaure boundary
- and prior to any reactor to conducted in accordance with the prost. down for refueling or approximately every ates of the American National Standard 18 months, whichever occurs Srst, until two es a rate sta as app tc b o aball 48 4 1972, wane Rate Wating M Con. consecuun W A testa meet the acceptance conducted in accordance with the following.
'atn'^mnt 8tructures for Nuclear Reactors. criteria tn IL a.d(b), after which time the A. Type A test--l. Pretest requirements. March 101972.s De method chosen for the retest schedule spectaed in IIID. may be (a) Containment inspectfan in accordance Initial test shall normauy be used for the resumed.
periodio ?"sta.
B. Type 8 rests.
with V.A. shall be priormed as a prerequialte to the performance of Type A testa. During. (b) The accuracy of any Type A test shall
- 1. Test methods. Acceptable means of per.
the period between the inattauon of the con. be ver!!.ed by a supplemental teet. An accept. forming a preoperational and periodic Type tainment inspection and the performance of able method is described in Appendia C of B tests include:
ANSI Men 4-1972. The supplemental test (a) irwamination by halide leak. detection the Type A test, no repairs or adjustments method selected shan be conducted for aufB. method (a by ot.her equivalent test methods be d
ea " condition c ent durstle to estabush accurately the such as maae spectmneter) of a test cham.
as practical. During the period between the change in leakage rate between the Type A ber, pressurtsed with air, nitrogen, or pneu.
completion of one *ype A test and the initta* and supplemental test. Results from this matic f!uld spectaed in the technical tion of iM wentsinment inspection for the supplemental test are acceptable provided spec 1Scauons or associated bases and con.
ad us the difference between the supplemental test structed as part of individual containment
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data and the Type A test data la within 0.25 penetrations.
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La ( r 0.25 Lt),It results are not wt'.'n"e~ter*
(b) Measurement of the rate of pressure leakage escoeda that spectaed in the technical I4 (r. 5 Lt), the reason sha!! be d spectScation as soon as practical after iden.
toes of the test chamber of the containment t1acation. It during a Type A test. Including mi ed, corrective action taken, and a suc*
penetration pressurtzed with air, nitrogen, the supplemental test spec 18ed in IILA.3.(b), C888ful 8Upplemental les performed, or pneumatto Suld spec 18ed in the technical potentia 117 escesolve leakage paths are iden.
(c) 'I et leakage rates shall be calculated spec 1Scations or associated bases.
t18ed which wiu interfere with mattefactory using abe lute values corrected for instru.
(c) Leakage surveulance by means of a mmpleuon of the test, or which result in the
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- permanently tnataued system with provisions Type A test not meeting the acceptance ert.
- 4. Preopersifonal leakage rate tests. (a) for continuous or intermittent pressurisation
. teria III.A.4.(b) or IILAA.(b), the Type A test Test pressure-(1) Reduced pressure tests. of individual or groups of conhtnment pene.
shall be termineted and the leakage through (1) An initarJ test shall be performed at a trations and measurement of rate of pres.
such paths shall be measured using local pressure Pt. not toes than 0.50 Ps to measure ours loss of air, nitrogen, or pneumatic fluid leakage testing methods. Repaire and/or a leakage rate Ltm.
specified in the technical spec 1Scation or adjustments to equipment shall be made and (11) A second test shan be performed at associated bases through the leak paths.
a Type A test performed. ne corrective ac. Pressure Pm to moneure a leakage rate Imn.
- 2. Test Pressure. All preoperational and j
i tnon taken and the change in leakage rate (ui) he leakage characteristlos yielded periodic Type B testa shall be performed by determined from the tests and.overall inte. by gneesurements Ltm and Lam shall estab. local pneumatic pressurtzstion of the con.
grated leakage determined from the local leak lash the mastmum allowable test leakage tainment penetrations, either individually or and Type A testa shall be included in the rate Lt M not more than La (Ltm/ Lam). In in groups, at a pressure not less than Pa.
report submitted to the Commission as spe. the event Ltm/Imn is greater than 0.7, Lt
- 3. Acceptance ersterta. (See also Type C cified in V.B.
shall be specifled as equal to 14 (Pt/Pa)u, testa.) (a) ne combined leakage rate of all (b) Closure of containment teolat4on valves (2) Peak presure tests. A test aball be per. penetrations and valves subjeco to Type B for the Type A test sha!! be accompitched by formed at pressure Pa to measure the leakage and C tenta shall be less than 0.60 La. with normat operation and without any prettml. rate Lam.
the exception of the valves speciSed in nary esercising or adjustmente (e.g.,
no (b) Acceptance criterta-(t) Reduced III.C.3.
tightening of valve after closure by valve pressure tests. The leakage rate Ltm abau be (b) r==kage measurements obtained motor). Repatra of matoperating or leaking lean than 0.76 Lt.
valves shall be made as necessary. Informa.
through component leakage surveluance sys.
tion on any valve closure snalfunction ce (2) Peek pressure tests. The leakage rate terna (eg., continuous pressurisation of in.
Lam ahall be less than 0.75 La and not greater dividual containment componenta) that valve leakage that foquires correctlye action than Ld.
maintains a pressure not less than Pa at in.
before the test, shall be included in the r**
- 8. Periodfo leshaps rate tests--(a) fest pres, dividual test chambers of containment pene.
port submitted to the Comm1anton as speCl* sure. (1) Reduced pressure testa shan be trations during normal reactor operation, j
fled in V.B.
conducted at Pt. ;
are acceptable in 11eu of Type B tests.
(e) he containment test conditions shall (2) Peak pressure testa shall be conducted C. Test C tests.
J stabilise for a pertod of about 4 houre prior at Pa.
to the start of a leakage rate test.
- 1. Test method. Type C tests sha!! be per.
(d) hose portions of the fluid systems formed by local pressurization. The pressure shall be applied.in the same direction as that are part of the reactor coolant prosau.e
- ANSI N45.4-1972 Leakage Rate Testing of that when the value would be required to tn.undary and are open directly to the con. Conhinmant structures for Nuclear Iteactors perform Sta safety function, nulesa it can tainment atmosphere under poet. accident (dated Mar. 16, 1972). Copies may be ob.
be determined that the resulta from the tests conditions and become an extenaton of the tained from the Amer!can Nuclear Society, for a pressure applied in a different direction boundary of the containment sha!! be opened 244 East Ogden Avenue. Hinadale. IL 60521. ' will provide equivalent or more conservative or vented to the containment atmosphere A copy is available for inspection at the prior to and during the test. Portions of Commission's Public Document Room.1717 results. De test methods in III.B.1 may be substituted where appropriate. Each valve to onceed eystaans tassee concalament that pene, R 8treet NW., Washington. DC. The incor.
trate sentatmaat and repture as a result of be tested shall be closed by normal opera.
a lone of coolant accident shall be vented to permatom by reference was approved by the tion and without any pre!!minary exercising Director of the Pederal Regia.er on Octo.
the containment atmosphere. A!! vented sys. ber 30,1972.
or adjustments (e g., no tightening of valve i
after closure by valve motor).
PEDERAL RE4157tt, VOt. 33, NO. 30- WEONE50AY, FE8tUARY 14,1973
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