ML19331E283
| ML19331E283 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/03/1980 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19331E280 | List: |
| References | |
| NUDOCS 8009090560 | |
| Download: ML19331E283 (1) | |
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s, l'IMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
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3.7 CONTAINMENT SYSTEMS 4.7 CONTAINME$r SYSTEMS 2.a.
Primary containment integrity 2.
Int'egrated Leak Rate Testing
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shall be maintained at all times when the reactor is Primary containment nitrogen critical or when the reactor consumption shall be monitored water temperature-is above once each 8-hour shif t to 212'F and fuel is in the determine the average daily reactor vessel'except while ni'trogen consumption for the performing "open vessel" last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Excessive leakage physics tests at power lavels is indicated by a N2 consuspelon not to exceed SMW(t).
rate of 27. of the primary con-tainment free volume per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> b.
Primary containment integrity (corrected for drywell tenperature, l
is confirmed if the maximum pressure, and venting operations) allowable integrated leakage at 49.6 psig. Corrected to normal rate, La, does not exceed dryvell operating pressure of 1.5 the equivalent of 2 percent psig, this value is 549SCFE. If of the primary containment this value is exceeded, the action volume per 24 h'ours at the specified in 3.7.A.2.C shall be
~j 49.6 psig design basis taken.
accident prestare, Pa.
The containment leakage rates c.
If N2 makeup to the primary shall be demonstrated at the containment averaged over following test schedule and shall 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (corrected for be determined in conformance with pressure, temperature, and the criteria specified in Appendix J venting operations) exceeds to 10 CFR 50 using the methods and 549 SCFH, it must be reduced provisions of ANSI N45.4(1972).
to 549 SCFH within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or the reactor shall be placed a.
Three type A tests (overall in hot shutdown within the integrated containment leakage next 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />.
rate) shall be conducted at 40110-month intervals during shutdown at either P, 49.6 psig, a
or at.P 25 psig, during each 10-yearplantinserviceinspectfun.j;;
g b.
If any periodic type A test fails to meet either 0.75 L or 0.75 4
L the test schedule :or sub-e sequent type A tests shall be reviewed and approved by the l
Commission.
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If two consecutive type A tests fail to meet either 0.75L or 0.75 L a type A test sh$11
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be perEo,rmed at least every 18 months until two consecutive 233 5mo90N i~
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