ML20050D076
| ML20050D076 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 04/01/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20050D078 | List: |
| References | |
| NUDOCS 8204120047 | |
| Download: ML20050D076 (16) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION l
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CO M ONWEALTH EDISON COMPANY DOCKET NO. 50-237 DRESDEN NUCLEAR' POWER STATION UNIT 2 AMENDMENT TO PROVISIONAL OPERATING LICENSE Ac.endment No. 68 License No. DPR -19 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Commonweal'th Edison Company (the licensee) dated November 30, 1981 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will o)erate in conformity with the ' application, the provisions of tie Act, and the rules and regulations of the Connission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical
~
Specifications as indicated in the attachment to this license amend-i ment, and paragraph 3.B of Provisional License No. DPR-19 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 68, are hereby incorporated l
in the license.
The licensee shall operate ~the facility in accordance with the Technical Specifications.
e204120047 820401 PDR ADOCK 05000237.
P PDR A
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This license amendment is effective as of the'date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
- !' N Dennis M. Crutchfield, ief Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications
. Date of Issuance:
April 1, 1982 i
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ATTACHMEfiT TO LICEflSE AMENDMENT NO. 68
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PROVISI0ftAL OPEPATING LICENSE NO. OPR-19 i
DOCKET NO. 50-237 Revise the Appendix "A" Technical Specifications as follows:
Remoye P.eplace 108a 108a 109 109 110 110 111 111-115*
112 113 114' 115 130 130 i
- Pages 111-.115 are now intentionally blank.
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3.7 LilllTIllC CollDITIOli FOR.0PEitATIO!I 4.7 SURVEIIldllCE REQUIRT.i!EliTS above.
In connection with sucli testing, d.
A visual inspection of the' suppression chamber tiie pool temperature must be reilucevi to interior, including water line regions, shall below the normal power operation limit be made at each major refucting outage.
specified in (1) above within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
i (3) The reactor shall be scrammed from any operating condition if the pool tempera-ture reaches 110*F.
. Power operation shall not be resumed until the pool temperature is reduced below the normal power opera-tion limit specified in (1) above.
(4) During~ reactor isolation conditions, the reactor pressure vessel shall be depres-surized to lens than 150 psig at normal cooldown rates if the pool temperature a
reaches 120 F.
d.
Plaximum downcomer submergence is 4.00 ft.
'ci Illnimum downcomer submergence is 3.67 f t.
I f.
If specifications 3.7. A.l.a or 3.7. A.1.b are not met and suppression pool water volume cannot be restored within the subsequent six (6) i hour period, an orderly, shutdown shall be d
initiated and the reactor shall be in a cold l
shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4 108a
.\\mendment No. 68
3.7 1.'llitTitic CollDIT10Il FOR OPERATIOli 4.7 ' SURVEILLAllCE REQUlitEllElfTS l
2.
Primary containment integrity shall be maintained 2.
The primary containment integrity shall be demon-at all times when the reactor is critical or phen strated by conducting Primary Containment Leak the reactor water temperature is above 212*F and Tests and shall be determined in conformance with fuel is in the reactor vessel except while per-the criteria specl(ied in Appendix J of 10 CFR 50 forming low power physics testo at atmospheric using the methods and references therein.
pressure at power levels not to exceed 5 !!w(t).
a.
.Three Type A tests (Overall Integrated Con-n.. Primary containment 1.cakage rates are defined tainment Lenkage Rate) shall be conducted at from:
spproximately equal intervals during each 10 year plant in-ser'vice. inspection interval at (1) The calculated peak containment internal either Pa or Pt with the last being donc
- pressure, P,,
is equal to 48 psig, during the 10 year in-service inspection shut-d own '.
(2) The containment vessel reduced.t.es_t-pressure, P, la equal to 25 psig.
b.
If any' periodic Type A test falls to meet g
either 75 percent of L or 75 percent of L e t
(3) The maximum allowable leakage rate at a the test schedule for subsequent Type A testa pressure of P,
L,,
is equal to 1.6
'shall be reviewed and approved by the Commission.
9 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 40 psig.
c.
If two consecutive Type A tests fail to meet either 75 percent of L, or 75 percent of L.
t a Type A test shall be performed at each shut-(4) The maximum allowable test Icakage rate at a preneure of Pt, Lt is lesn than or equal to
.down for refueling or approxirmately every 18 1.n (Ltm/ Lam).
If Ltm/L is greater th n 0.7, months until two consecutive Type A tests Lt is(specifiedasequaYto)La (P /Pa) meet the above requirements, at which time t
the normal test, schedule may be resume,d.
(5) The total mensured leakage rates at
)
pressures of P, and Pt are 1,nm and L d.
The accuracy of each Type A test shall be tm, respectively.
, verified by a supplemental test which:
b.
When primary containment Integrity is re-(1) Confirms the accuracy of the test by quired, primary containment leakage rates verifying that the difference between shall be limited to:
the supplemental data and the imposed leakage is within 25 percent of La or (1) An overall integrated leakage rate for-25 percent of L h t
Type A testa of:
(2) lies a duration suf ficient to establish (a) Lam less than or equal to 75 gier-accurately the change in Icakage rate cent of La.
between the Type A test and the supple-(b) Lim less than or equal to'75'per-mental test.
cent of L -
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Amendment No. 68
3.7 LIltlTIllG C0!!DITI0li FOR OPEll ATIOli 4.7 SURVELLIAllCE REQUIREttElfTS (2)
(a) A combined Icakage rate of Ices'than (3) Requires the quantity of gas injected or equal to 60 percent of Ia for all Into the containment or bled from the testable penetrations and isointion containment during the supplemental test valves euhject to Type H and C tests to be equivalent to at least 25 percent except for main steam isointion of the total measured leakage at P, or P. '
t valves.
e.
Type B and C teste shall be conducted at Pa, (h) A Icakage rate of less than or equal at intervals no greater than 24 months except to 3.75 percent of La for any one for tests involving:
air lock when pressurized to 10 peig.
(1) Hain steam line isolation valves which (c)
'11.5 SCF per hour for any main steam shall be tested at a pressure of 25 psig
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isolation valve at a test pressure of each operating cycle.
25 poig.
(2) Bolted double-gasketed seals which shall be ~t'ested at a pressure of 48 psig when-ever the seat is closed after being a
opened and each operating cycle.
(3) Air locks which shall be tested at to pelg each operating cycle.
f.
Continuous Lenk Rate'Honitor I
(1) When the primary ~ containment is inerted,
.the containment shall be continuously
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' monitored for gross leakage by review of the inerting system make-up require-i ments.
(2) This monitoring system may be taken out of service for the purpose of maintenance or testing but.shall be returned to service as so'on as practical.
- g. - The luterior surf aces of the drywell shall be j
visually (nopected each operating cycle for evidence of deterioration.
E Amendment No. 68 110
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.n based on the AEC gulita for developing sock reto leak rata is 1.6I/
testing and surveillance of reactor containreent The maximia allowable test Thio value for yes, ele (14). Allowing'the tent intervata to be d.sy at a pressure of 40 pnig. test condition was derived f rom the m.txtraura extended up to 8 months permits some flex-the leak rate of about 2.02/ day Ibility needed to have the testa coincide with allownble accident i
t when enrrected for the effecto of conta nmen
. scheduled or unscheduled shutdown periods.
~
ditions.
environment under accident and test con The data reduction methods of the applicable ANSI in the accident. cane the containment atenoophere Initially would be compoacd of stensa and hot. air standard will be applied for the integrated Icak uberena under test conditions the test me rate tests as specified in Appendix J of 10 CFif 50.
d lure
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i would be air or nitrogen at arablent condit ons.
The penetration and. air purge piping leakage Considering the differences in mixtura compo-icek the appropriate correc-test frequency, along with the containment n! tion and temperatures, tion factor applied was 0.0 and deterimined rate testa, la adequate to allow detection of fr""
Whenever a double-gasketed tha guide on containment testing (13).
leakage trends.
the penetration (primary containment hesd Although the dose calculations suggest that equipment batches and the suppression chamber the space access hatch) is broken and rereado, accident leak rate could be allowed to increase 3.2%/ day before the guideline thyroid between the gankets la pressurized to detensiina The that the seals are perforraing properly.
doso value given in 10 CFit 100 would belimit of 1.61/
test preneura of 4,8 peig la consistent with the to about
' emceeded, establishing th'a tent day psovides an adequate snargin of anfety to.
accident analyses and the maximum preopern-It. is expceted I
l annure the health and safety of the generala further conoidered that the allow-that the reajority of the leakage tional leak rate test pressure.
from valves, It into the scactor public. leak rate should not deviato nignificant1Y penetrations.and seals would be Ilowever, it is poonible that leakage f rom the containn>ent doelgn value to takedesign lenk-tlahtueno capnhilitT nhle pullding.
,1nto' other parts of the f acility could occur.
advantage of thestructure over.its nervice lifetime.
Such leakage paths that may affect significantly Additional svirgin to maintain the containiment
'the consequences of accidents are to be of the The personne1' air lock is tested in thn "an built" condition is achievnd.by lenk rate.
.minimited.
catahl f ahing the allowable operational 10 pnig, becaune the inboard door' is not l
The allouable operational. leak rate in derived designed to shut in the opposite direction.
at by multiplying the mamlmws allowablo leak rato
. fha results of the-loan-of-coolant accident Icak rate or the allownbic test analyses presented in Amendment fio. 18 of the l
i i 25% mar-
.by 0.75 thereby prov d ng a hich may gin to allow for Iankage detarloration woccur du' ring the period between leak rate TID 20583. Leakage Characteristice of Steel tents.
(13) Containment Vennel and the Analysis of 1.caksi The primary containment leak rate teet f ra.
Rate Determinntions.
quency is based on snaintainJng adequate annut, Technical Safety Guide " Reactor Containmant that the leak rate reisnina within the (14) ' Leakage Testing and Surveillance llequirements l The leak rate frequency la ance USAEC, Division of Saf ety Standards, Revised specification.
Draft, December 15, 1966.
s3a Amendment No. 68
/
'o UNITED STATES
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",h NUCLEAR REGULATORY COMMISSION g
E WASHINGTON, D. C. 20555
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-249
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DRESDEN NUCLEAR POWER STATION UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 60 License No. DPR-25 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Comonwealth Edison Company (the licensee) dated November 30, 1981 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in.accordance with 10 CFR Part 51 of.the Comission's regulations and all applicable requirements have been satisfied.
l 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amend-ment, and paragraph 3.8 of Facility Operating License No.'DPR-25 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 60, are hereby incorporated in the license.
The licensee shall operate.the facility in l
accordance with the Technical Specifications.
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3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications J
Date of Issuance: April 1, 1982 3
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ATTACHMENT TO LICENSE AMENDMENT NO.60
' FACILITY OPERATING LICENSE NO. DPR-25 DOCKET N0. 50-249
. Revise the Appendix "A" Technical Specifications as follows:
Remove Replace 108a 108a 1 09 109 110 110 111 111-115*
112 113 114 115 130 130
- Pages 111-115 are now intentionally blank.
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3.1 I,lillTIIK; C011D171013 F0lt ol*r.itATIoli
- 4.7,, SUltVEll,1.A! ICE ItE't}UlitEllEtrTS above.
I:3 connect ion wit h auch tent ing, d.
A visuni innpection of the' suppression chamber the pool temperature must be reduced.to interior, including water line regions, shall below the normal power operation limit be made at each major refueling outage.
.npecified in (1) above within 24 hourn.
g, (3)' The renctor shall be ner nmed f rom any operating condition if the pool tempern-ture reachen l10*F.
Power operation chall not ~be resumed until t.he pool temperature in reduced below the normal power opern-tion limit specified in (1) above.
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(4)
During reactor loolntion conditions, the e'
renctor preneure venac1 shall be depren-nurized to lenn thnn 150 pelg at. normal cooldown raten if the pool temperature reachen 120 F.
d.
Ilaximum downcomer submergence is 4.00 ft.
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c.
llinimum downcomer-submergence le 3.67 ft.
s f'.
If specifications 3.7.A.1.a or 3.7.A;1.b are not met and suppression pool water volume
';i cannot be restored within the subsequent six (6)_
hour period, an orderly shutdown shall be initiated and the reactor shall be in a cold l
shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
.t I-100s Amendment No.,56.,.60
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3.7 1,'llitTIllG C0!IDITIO'll TOR OPERATIO!I 4.7 SURVEILLANCE REQUIREHEttfs 2.
Primary containment integrity shall be maintained 2.
The primary containment integrity shall be demon-at all times when the reactor is critient or when strated by conducting Primary Containment Leak the reactor water temperature in above 212*F nnd Tests and shall be determined in conformance with fuct in in the reactor vessel except while per-the criteria specified in Appendix J of 10 CFR 50 forming low power physics tents at atmospheric using the methods and references therein, pressure at power levels not to exceed 5 tlw(t).
a.
Three Type A tests (overall Integrated Con-a.
Primary containment Icaknge rates are defined tainment Lenkage Rate) shall be conducted at
'from:
spproximately equal intervals during each 10 year plant in-service-inspection interval at (1) The calculated peak containment internal either P or Pt with the last being donc a
pressure, P,, is equal to 48 psig, during the 10 year in-service inspection shut-down.
(2) The containment vessel reduced t. cst-pressure, Pt e. in equal to 25 pelg.
b.
If any ~ periodic Type A test falls to meet I
either 75 percent of L or 75 percent'of L.
a t
(3) The maximum allowable Icakage rate at a the test schedule for subsequent Type A teste pressure of P, 1,,,
is equal to 1.6 shall be reviewed and approved by the Commission, i
9 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 40 peig.
c.
If two consecutive Type A tests fall to meet either 75 percent of L, or 75 percent of L.
t (4) The maximum allowable test Icakage rate at a Type A test shall be performed at each shut-a preneure of P, Lt,in icon thnu or equal to down for refueling or approximately every 18 t
l.a (htm/ Lam).
If Ltm/ Lam is greater thqn 0.7,
'nonths until two consecutive Type A teste Lt io (specified as equal to) 1.a (P /Pa)3 meet the above requirements, at which time t
the normal test schedule may be resumed.
(5) The t'otal measured lenkage rnten at j
preneurce of P, and pt "T"
I'am and Ltm, d.
The accuracy of each Type A test shall be renpectively.
yerified by a supplemental test which:
b.
When primary containment integrity is re-(1) Confirms the accuracy of the test by quired. primary containment Icakage rates verifying that the difference between shall be limited to:
the supplemental ~ data and the. imposed leakage in within 25 percent of La or (1) An overall integrated Icakage rate for 25 percent of L '
t Type A testa of:
(2) lins a duration sufficient to establish (a) Lam Idas than or equal to 75 per-accurately the change in Icakage rate cent of La.
between the Type A test and the supple-mental test.
(b)
L~tm Ices than or equal to 75 per-cent of L -
t
'l09 Amendment No.
60
3.7 LIlllTitIG C0!!DIT10tl FOR OpEltATIOll 4.7 BURVEILLAllCE REQUIREllElrTS (2)
(n) A combined Icaknge rate of less than (3). Requires the quantity of gas injected into the containment or bled from the or equal to 60 percent of La for all containment during the supplemental test testabic penetrations and isointion valves subject to Type B nnd C t'ests to be equivalent t6 at Icast 25 percent except for main. steam isointion of the total mescured Icakage at P or P.t valves.
e.' Type D and C teste shall be conducted at Pn, (b) A leakage rate ~of less than or equal at intervals no greater than 24 months except to 3.75 percent of La for any one for tests involving:
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air lock when pressurized to 10 psig.
(1) !!ain steam line isolation valves which (c) 11.5 SCF per hour for any main steam shall be tested at a pressure of 25 poig isolation valve at a test pressure of each operating cycle.
25-peig.
(2) Dotted double gasketed seals which shall be tested at a pressure of 48 pelg when-ever the sent is closed af ter being opened and each operating cycle.
t (3) Air locks which shall be tested at to pelg each operating cycle.
f.
Continuous Leak Rate Honitor l
(1) When the primary containment is inerted, the containment shall be continuously j
l monitored for gross lenkage by review of'the fuerting system make-up requ/cc-ments.
(2) This monitoring system may be taken out of service for the purpose of maintenance or testing but shall be returned to acrvice as soon as practical, g.
The interior surfaces of the drywell shall bc j.
visually inspected each operat'ing cycle for evid.cnce of deterioration.
,4 4
e Amendment No. 60 110
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u um u 3.7 LilllTIlic C0tIDITIOli FOR Ol'ERATIOff 4.7 SURVEILLA!1CE REQllIREttElRS
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Pages _11-115 a re 'inten t.ionall'y blank.
Amendment No. 60 til -
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'Ibc maailmura allowable t e s t leak ratn is 1. f,I/
baced cn.ths AEC guido for developing acek rato day at a pressure of 40 polg.
'Ihla value for testing and surveillance of reactor containstent the test condition was derived f rom the maalinute ve s sels (14). Allowing'the test intervals to be allowable accident leak rate of about 2.0I/ day extended up to 8 months permits some flex-when corrected for the effecta of containment Ibility needed to have the tests coincide with environment under accident and test conditions.
scheduled or unscheduled shutdown periods.
In.the accident cane, the containreent atmoophore 8
- /-
Initially would be composed of steam and hot mir
.The da'ta reduction methods of the applicable AtiSI whereas under test conditions the tes t medlure standard will be applied for the integrated leak would be air or nitrogen at ambient conditions.
rate testa as specified in Appendix J of 10 CFR 50.
Considering the differencee in mixtura compo-altion and temperatures, the appropriate correc-The penetration and air purge piping leakage tion f actor applied was 0.8 and determined f rom test frequen'cy, alosig with the containment leak the guide on containiment testing (13).
rate tests, is adequate t'o allow detection of leakage, trends. Whenever a double-gasketed Although the dose calculations suggest that the penetration (primary containment head accident leak rate could be allowed to increase equipment hatches and the suppression chamber to al,out 3.2%/ day before the guideline thyroid access hatch) is broken and ressado, the space dous value given in 10 CFR 100 would be betueen the gaskets is pressurized to determine
'y exceeded, entablishing the tent limit of 1.6%/
that the seals are perforveing properly. The day provides an adequata margin of safety to test pressure of 48 pelg la consistent with the casure the health and safety of the general accident analyses and the maximum preopera-
. 'public.
It is further considered that the allotr-tional lesk rate test pressure.' It is expected n ts t e Icak rate should not deviate significantly that the majority of the leakage from valves, f rom the containment design value to take penetrations and seals would be into the scactor advantage of the design leak-tightness capability building.
However, it is possible that leakage of the structure over ita'aervice lifetime.
Into other parts of the facility could occur.
Additional margin to maintain the containisent Such leakage patha that may affect algnificantly
.in ihn "as built" condition la schieved by the consequences of accidents are to be notablishing the allowable operational. leak rate.
miniselred. The personnel air lock is tested The allowablo operational leak rate le derived at 10 paig..because the inboard door Is not by multiplying the maulinina allowable leak 1 rate designed to shut in the opposite direction.
or the allowabic test Icak rate by 0.75 thereby providing a 25% mar-The results of the loss-of-coolant accident gin to allow for leakage deterioration which maY analyses presented l'n Amendment No. 18 of the occur during the period between. leak rate tests.
The. primary containment leak rate test fre.
(13) TID 20583, Leakage Characteristica of Steel quency la based on maintalning adequate assur-Containment Vensel and the Analysis of 1.cakeg ance that the leak rate remalns within the Rate Determinations.
npccification.
The leak rate frequency is (14) Technical Safety Guide, " Reactor Containment;
- l Leakage Testing and Surveillance Requirement $
USAEC, Division of Safety Standards, Revised Draft, December 15. 1966.
t Amendment No. 60 pso
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