ML19319D802
| ML19319D802 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 02/14/1973 |
| From: | US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19319D793 | List: |
| References | |
| NUDOCS 8003250797 | |
| Download: ML19319D802 (2) | |
Text
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o b
J O
RULES AND REGULATIONS E
ston. The proposed rule would not have j
required the reporting of such informa-tion unless attempts to reduce the leak-age rate of poor leak-tight components failed to meet minimum leak-tightness acceptance criteria. Thus, components which required frequent adjustments or repair in order to meet allowable leak-
)
age limits will be identified and the spe-cific reductions in leakage rate values, resulting from such adjustments, will be reported to the Commission. The identi-f! cation of such components will pron:ie l
the AEC with a sounder basis for judging whether or not containment leakage 1
rates could have been exceeded in the unlikely event a design basis accident
]
were to occur. In addition, such identi-fication may provide insight into the fre-Title 10-Atomic Energy quency and kinds of adjustments being l
made to components to meet the mini-J CHAPTER 5-ATOMIC ENERGY mum acceptable leakage limits and a l
COMMISSION basis for either establishing a more fre-PART 50 -UCENSING OF PRODUCTION quent containment leakage test schedule.
AND UTlu2ATION FACILITIES or modifying or replacing components.
Reactor Containment Leakage Testing for With regard to item (2) above, the WaterCooled Power Reactors rule set forth below specifies criteria by which the licensee may for certain On August 27,1971, the Atomic Energy safety-related Systems temporarily dis-r'nmmtuton published in the FrDERAr* pense with drainage and venting to Con-RacIsvua (36 FR 17053) a proposed tainment atmosphere during Type A amendment to its regulations in 10 CFR containment leakage tests. The proposed Part 60 which would specify the mini
- rule had specified that all systems which mum containment leakage test mquire-would connect directly with the contain.
ments for water-cooled power reactors.
ment atmospeere 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. Strtet for consideration in connection with the comp!!ance wit!* "lis rule would have re-proposed amendment within 60 days quired removi certain safety-related after publication in the Frosmar. Rzars-systems frorn service for the duration of vna. Upon consideration of the comments the test and would hmit the performance received, and other factors involved, the of the overall integrated containment Cnmmianton has adopted the proposed leakage tests to those times when there amendment, with certain modifications would be no fuel in the reactor, This in the form set forth below.
procedure is considered to be unneces.
Rfgntecent differences from the sarily conservative.
maandmant published for enmment are:
The inclusion of all safety-related sys-(1) Modificablesa of procedures govern-tems in the oversal integrated contain-ing ccntainment inspection and leak de-ment leakage test can be accomplianed taction surveys, as a prerequisite to con-while the reactor is fueled, and in a state ducttng formal leakage tests, and clarift-of potential criticality, by maintaining cation of the basis for reporting pretest the minfmum number of safety-related leakage values to the Commisstnn (2) systems in an operable state until all estahnahment of criteria for deferring systems are tested. Another option is to certain safety-related systems from res-periodically test the containment isola-utarly scheduled Type A containment tion valves in these safety-related sys-leakage tests. (3) incorporation by refer-tems in accordance with the rule set ence of the recently-1ssued American forth below. This would also assure that National Standard for leakage rate test-the requisite level of plant safety will be Ing of containment structures for nuclear provided during the containment leak-reactoes into the regulation. (4) inclu-age test program without comp'omising i
ston of nitrogen gas as.s suitable testing the requirements for including all sys-anodium for testing the lenktightness of tems which penetrate the containt' tent valves, and (5) inclusion of water-leak-boundary in the leakage test.
ago 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 contatnment 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 addition, editorial and format American National Standards Institute changes were made.
approved ANS 7.60 and of:1cially issued l
With regard to item (1) above, the it for use as ANSI N45.4-1972 American rule set forth below mquires the licensee National Standard. "Ieakage Rate Test.
to idatify specifically those componenta ing of Containment Structures for Nu-whose initial poor leak tightness per-clear Reactors." The standard has been formance precluded completion of a reviewed for compatibility with the pro-Type A containment leakage test and to posed rule and it was concluded that in-report this information to the Chmmtm. corporation of the requirements of ANSI MDesAt asO4579u, VOt. 38, MO. 30-WEoNf50AY, FEBRUARY 14,19r3 8003 250 7f 7
d RULES AND REGULATION.
SM from test *ug the containment with compo. tems shall be drained of water or other Sutds (b) Acceptance criterM-(1) Reduced nonta ar.2 systems in the state as cicae as to the extent necesaary to nasure exposure of pressure tests. The leakage rate Ltm shall be practical to that which would esist under the system containment isolation valves to less than 0.75 Lt. If local leakage measure-design basta accident co.2ditions (e g., vented, containment air test pressure and to assure ments are takcn to efect repairs in order to drained. Sooded or pressurtzed),
they will be subjected to the post-accident meet the acceptance criteria, these measure-O. "Acca, stance criterta means the stand. d!Serential pressure. Systeme that are re. menta shall be taken at a test pre'ssure Pt.
ard against which tent results are to be quired to maintain the plant in a safe con.
(2) Fesk pressure testa shall be conducted compared for estabitshing the functional ac.
dition during the teet shall be operable in Lam shall be less than 0.75 La. If local lesa-ceptability of the containment as a leakage their normal mode. and need not be vented. age measurements are taken to eSeet resa.n limiting boundary.
Systerna tha; are normally 81'ed with water in order to meet the acceptsace cnte r'.a.
III. f.raraos TzsTINo RzetrtszurxTe and operating under post-accident cendt. these measurements shall be taken at a ten tions, such as the containment heat removal pressure Pa.
A program consisting of n achedule for con. system need not be vented. However. the 6.
Adottio' sal Requirements. (an If any ducting Type A B. and C testa shau be de.
containment 1 solation valves in the systema periodic Type A test falls to meet the appu.
veloped for leaJt testing the primsry reactor defr.rd in m.A.I.(d) shall be ented in ac. cable acceptance criteria in III.AA(b). the containment and related systems and compo. cordance with III.C. he measured leakage test schedule applicable to subsequent Type nonta penetraung primary containment pres. rate from these testa shall be reported to the A testa win be reviewed and approved by the sure boundary.
Comm!anton.
Commisalon.
Upon completion of construction of the
- 2. Conduct of tests Preope,ttonal leakage (b) If two consecutive periodic Type A primary reactor containment. Including in.
rate testa at either reduced oc at peak pree. tests fau to meet the applicable acceptance stallation of all portions of mechanical Suid, sure. shall be conducted at the intervals criteria in ITI.A.5(b) notwithstanding the electrical, and instrumentation systema pene. 8pec18ed in M.
periodic ntest schedule of E a Type A trating the primary reector containment
- 3. Test methods. (a) AU Type A testa shall test shall be performed at each plant shut.
pressure boundary, and prtor to any reactor be conducted in accordance with the provt. down for refueling or approximately every operating period preoperational and periodic stons of the American National StanM 18 months. whiche occurs Snt. untu tu j
leakage rate tests, sa applicable, shall be N48.4-1972 Imakage Rate Testing of Con. consecutive Type A testa meet the acceptance l
conducted in accordance with the following, tainment Structures for Nuclear Reactors. criteria tn III.A.5(b). after whach time the A. Type A test-1. Pretest requirements. March 161972.s The method chosen for the retest achedule spec 13ed in IILD. may te (a) Containment inspection in accordance Initist test shall normally be used for the resumed.
periodic tests.
p B. Type B tests.
l "h"anc (b) The accuracy of any Type A test shall
- 1. Test methods. Acceptable means of per.
j of A te, g
the period between the initiation of the con. be veriaed by a supplemental tiest. An accept. forming a preoperational and periodic Type tainment inspection and the performance of able method la described in Ardis C of B M MW I
e sWental W the Type A test, no repairs or adjustmenta (a) hamm h M halth kaMmcWn 1
a i
shall be made so that the containment can method selected shall be conducted for au21 method (or by other equivalent test methods l
be tested in as close to the "as is** condition cient duration to establish accurately the such as maam spectrometer) of a test cham.
ma practical. During the period between the change in leakage rate between the Type A ber, pressurized with air, nitrogen, or pneu.
i completion of one Type A test and the initta. and supplemental test. Resulta from this matic f!uld specided in the technical 1
tion of the containment inspection for the supplemental test are acceptable provided spec 1Acations or associated bases and con.
subsequent Type A teet. repatra or adjust. the d1Rorence between the supplernental test stracted as part of individual containInent mente shall be made to components whose data and the Type A teet data la within 0.25 penetrations.
leakage exceeds that spec 1 Sed in the technical La ( r - Lt).If results are not within 0.25 4 (r Lt), the reason shall be deter *
(b) Measurement of the rate of precsure spec 1Acation as soon as practical after iden.
loss of the test chamber of the containment 113 cation. It d*tring a Type A test. Including i ed. wrectin action takan. and a suc*
the supplemental test spectaed in III.A.3.(b)
Ce88ful 8upplemental test performed.
penetration pressurized with air. nitrogen, or pneumat!c f!uld spec 1 Sed in the technical potentially excessive leakage paths are iden (c) '14st leakage rates shall be calculated spec 1Scations or associated bases.
ticed which will interfere with satisfactory using absolute values corrected for instru*
completion of the test. or which result in the I"*DI 8'TOF-(c) Leakage surveinance by means of a permanently instaned system with provisions Type A test not meeting the acceptance cr!.
- 4. PfeoPerational leakage rate tests. (a) for continuous or intermittent pressurization l
teria III.A.4.(b) or IILAE.(b). the Type A teeg Test pressure-(1) Reduced pressure fests. of individual or groups of containment pene.
j aball be terminated and the leakage through (1) An initial test shall be performed at a trations and measurement of rate of pres.
such paths shall be measured using local pressure Pt. not less than 0.50 Pa to measure sure losa of air, nitrogen. or pneumatic fluid leakage testing methods. Repairs and/or a leakage rate Ltm.
spectaed in the technical spectacation or adjustments to equipment shall be made and (11) A second test shall be performed at amaociated ha-a through the leak paths.
a Type A teet performed. 'Its corrective ac. Pressure Pa to measure a leakage rate f am-
- 2. Test Pressure. A!! preoperational and tion taken and the change in leakage rate
( 111 ) he leakage characteristics yielded periodic Type B tests shall be performed by determined from the testa and overall inte. by speasuremente Ltm and Lam aball estab. local pneumatic pressurization of the con.
grated leakage determined from the loca11eak 11ah the maximum anowable test leakage tainment penetrations, either individuauy or and Type A testa shall be included in the rate Lt ^f not more than La (Ltm/ Lam). In in groups, at a pressure not less than Pa.
report submitted to the Cornminalon as spe. the event Ltm/ Lam la greater than 0.7. Lt
- 3. Acceptance criteria. (See also Type C eloed in V.B.
shall be spec 1Aed as equal to la (Pt/Pa)k'. testa.) (a) The combined leakage rate of all (b) Closure of containment isolation valves (2) Peak presure tests. A test aba!! be per. penetrations and valves subject to Type B for the Type A test shan be accomplished by fornwt at pressure Pa to measure the leakage and C testa shall be less than 0.60 La. with normal operation and without any prelim!. rate Lam.
the esception of the valves spectaed in nary esercising or adjustments (eg no (b) Acceptance criterio-(t ) Jteduced III.C.3.
tightening of valve after closure by valve pressure taats. The Isakage rate Ltm ahan be (b) f = kage measurements obtained motor). Repaire of matoperating or leaking less than 0.75 Lt.
through component leakage surveillance sys.
Talves shall be made sa necessary. Informa.
(2) Peak pressure tests. De leakage rate tems (e g., continuous pressurization of in.
tion on any valve closure malfunction or Lam ahan be lees than 0.75 La and not greater dividual containment componenta) that valve leakage that foquires corrective action than Ld.
maintains a pressure not less than Pa at in.
)
before the test. shall be included in the ro*
- 8. Periodia leakage rate tests-(a) Test pres. dividual test chambers of containment pene.
port submitted to the Commianton as spect. ture. (1) Reduced pressure tests shall be trations during normal reactor operation.
Aed in V.B.
wonducted at Pt.1 are acceptable in 19u of Type B testa.
(e) The containment test conditions sha!!
(2) Peak pressure testa shall be conducted C. Test C tests.
stabilize for a period of about 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior at Pa.
to the start of a leakage rate test.
- 1. Test method. Type C testa shan be per.
(d) Those portions of the Auld systems formed by local pressurization. The pressure shall be applied.in the same direction u that are part of the reactor coolant pressure ANSI N45.4-1972 Leakage Rate Testing of that when the value would be required to boundary and are open directly to the con. Containment Structures for Nuclear Reactora perform its safety function, unless it can tainment atmosphere under post accident (dated Mar. 16. 1972). Copies may be ob.
be determined that the results from the tests conditions and become an estension of the tained from the American Nuclear Society, for a pressure applied in a different direction boundary of the containment shall be opened 244 East Ogden Avenue. Hinsdale. IL 60621. will provide equivalent or more conservattre or vented to the containment atmosphere A copy is available for inspection at the results. The test methods in IIIE 1 may be prior to and during the test. Portions of Commianlon's Pubite Document Room.1717 substituted where appropriate. Each valve to otomad aystems tmalde containment that pone. N Street NW Washington. DC. The incor. be tested shall be closed by normal opera.
tsste son *ahaat and rupture as a result of a lone of coolant ace! dent shall be vented to paration by reference was approved by the tion and without any preliminary exercising Director of the Pederal Register on Octo.
the containment atmosphere. Au vented sye. ber 30,1972.
or adjustments (e g. no tightening of valve after closure by valve motor).
MOEgAL hcl $ff t, V0t. 30, NO. 30--WEONESDAY. FigBUARY 14, 1973 1