ML20245H902
| ML20245H902 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/22/1989 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20245H907 | List: |
| References | |
| NUDOCS 8906300138 | |
| Download: ML20245H902 (2) | |
Text
__
Whers (L )
Design Basis Accident Leakage Rato 3
at Pressure P, L.-
~I' (L )
Maximum Allowable Test Leakage Rate at t
Reduced Test Pressure P Under Test Condition g
(L,g)
Maximum allowable operational leakage rate at pressure P, (Lg)
Maximum allowable leakage rate at pressure P t
(L,y)
Initial Measured Leakage Rate at Pressure l
a (Ltm)
Initial Measured Leakage Rate at Pressure t
(P,)
Peak Test Pressure of 59 psig (P )
Reduced Test Pressure of 30 psig t
4.4.1.1.3 Conduct of Tests Leakage rate tests should not be started until essential a.
temperature equilibrium has been attained.
Containment test conditions should stabilize for a period of about four hours prior to the start of a leakage rate test.
b.
The leakage rate test period shall extend to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of retained internal pressure.
If it'can be demonstrated to the satisfaction of those responsible for tne acceptance of the containment structure that the leakage rate can be accurately determined during a shorter test period, the agreed upon shorter period may be used.
Test accuracy shall be verified by supplementary means, such c.
as measuring the quantity of air required to return to the starting point or by imposing a known leak rate to demonstrate the validity of measurements.
1 d.
Closure of reactor building isolation valves for the purpose of the test shall be accomplished by the means provided for normal operation of the valves without preliminary exercised or adjustment.
4.4.1.1.4 Frequency of Test Af ter the initial preoperational leakage rate test, a set of three integrated leak rate tests shall be performed at approximately l
equal intervals during each 10 year service period, with the third i
test of each set coinciding with the end of each 10 year service period.
The test may coincide with the plant inservice inspection shut down periods.
8906300138 89062 PDR ADOCK 0500 P
80 Amendment No.121
t-V
^ y 4.4 REACTOR BUILDING 4.4.1 Reactor Building Leakage Tests Applicability
-Applies to the reactor building.-
Obiective To verify.that leakage from the reactor building is maintained within allowable -
limits.
Specification 4.4.1.1 Integrated Leakage Rate Tests 4.4.I.1.1 Design Pressure Leakage Rate
.The traximum allowable integrated leakage rate, L, from the reactor building at the 59 psig design pressure, P, shail not exceed 0.20L weightpercentofthebuildingatmosphereItthatpressureper.24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.4.1.1.2 Testing at Reduced Pressure The periodic integrated leak rate test may be performed at a test pressure, P, of 30 psig provided the resultant leakage rate, L,
doesnotexkeedapreestablishedfractionofL,determinedas.g follows:
Prior to reactor operation the initial value of the integrated a.
leakage rate of the reactor building shall be measured at design pressure and at the reduced pressure to be used in the periodic integrated leakage rate tests.
The leakage rates thus measured shall be identified as L,,
and L respectively.
tm L. shall not exceed L,~L, for values of L,
~
b.
t t
bblow 0.7 p
j
_ am, am 1
L, shall not exceed L,- P for values of L c.
t tm a6ove 0.7 p
g I
a am d.
If L /L is less than 0,3, the initial integrated test results shalk*be2ubjecttoreviewbytheNRCtoestablishanacceptable l
l a
value of L
- t Amendment No. 121 79
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