ML20093M605
| ML20093M605 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 10/11/1984 |
| From: | BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20093M600 | List: |
| References | |
| OL, NUDOCS 8410230040 | |
| Download: ML20093M605 (2) | |
Text
-
a a m :n
, ~ ~ a:p_ p
,, e i.
CONTAINMENT SYSTEMS l CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of:
346,000 SCCM) 0.20 percent by weight of the containment I
1 L,pe(r 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P, 50 psig, or 1.
air a
2.
1Lt (61,600 SCCH), 0.058 percent by weight of the containment f
air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a reduced pressure of P. 25 psig.
t b.
A combined leakage rate of < 0.60 L (207,600 SCCM), for all penetra-3 tions and valves subject to Type B $nd C tests when pressurized to P.
3 APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L SCCM) or 0.75 L (46,200 SCCM), as applicable, 4
or (b) with the 6ea(259,500sured combined leakage fate for all penetrations an subject to Types B and C tests exceeding 0.60 L, restore the leakage rate (s) to within the limit (s) prior to increasing the Reactor Coolant System temperature above 200'F.
SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4 -
1972:
I Three Type A tests (Overall Integrated Containment Leakage Rate) shall a.
be conducted at 40 + 10 month intervals during shutdown at either Pa (50 psig) or at P 25 psig) during each 10-year service period, t
The third test of :::h ::t shall be conduct:d during th: hutd ::: for,
th:-10 y cr plant inservice intpection.
CALVERT CLIFFS - UNIT 1 3/4 6-2 Amendment No. //,
0410230040 041011 PDR ADOCK 05000 P
ji:
is;.
l CONTAINMENT SYSTEMS 1:
CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage cate of:
f a (346,000 SCCM), 0.20 percent by weight of the containment 1.
<L air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,,
50 psig, or t (44,600 SCCM), 0.042 percent by weight of the containment 3
2.
<L air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a reduced, pressure of P. 25 psig, t
b.
A combined leakaae rate of < 0.60 L (207,600 SCCM) for all penetra-
+
tionsandvalvessubjecttoTypeB$ndCtestswnenpressurizedtoP.
3 APPLICABILITY: N0 DES 1, 2, 3 and 4.
ACTION:
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L SCCM), or 0.75 L. (33,400 SCCM), 'as applicable, t
or (b) with the Sea (259,500sured combined leakage rate for all penetrations valves subject to Types B and C tests exceeding 0.60 L, restore the leakage a
rate (s) to within the limit (s) prior to increasing the Reactor Coolant System temperature above 200"F.
SURVEILLANCE RE0VIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4 - 1972:
Three Type A tests (Overall Integrated Containment Leanage Rate) a.
shall be conducted at 40 + 10 month intervals during shutdown at (50 psig) or at P (25 psig) during each 10-year service either P,The third t :t of :ch Oct shall be conducted during-the t
period.
- hutd:.:n for th:-10 year plant focrvice impestrism CALVERT CLIFFS - UNIT 2 3/4 6-2 Amendment No. j!T,
.