ML20072D334
| ML20072D334 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/16/1983 |
| From: | ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20072D330 | List: |
| References | |
| NUDOCS 8303210283 | |
| Download: ML20072D334 (2) | |
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k 4.26 REACTOR BUILDING PURGE VALVES APPLICABILITY This specification applies to the reactor building purge supply and exhaust
-isolation valves.
OBJECTIVE
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JTo assure reactor building integrity.
SPECIFICATION 4.26.1-The reactor building purge supply and exhaust isolation valves shall be determined closed at least once per 31 days when containment integrity is required by TS 3.6.1.
4.26.2 Prior to' exceeding conditions which require establishment of reactor building integrity per TS 3.6.1, the' leak rate of the purge supply and exhaust isolation valves shall be verified to be within acceptable. limits per TS 4.4.1, unless the test has been successfully completed within the last three months.
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' BASES Determination of reactor building purge valve closure will ensure that reactor building integrity is not unintentionally breeched.
As a result of Generic Issue B-20, " Containment Leakage Due to Seal Deterioration," it was concluded that excess leakage past valve resilient seals is typically caused by severe environmental conditons and/or wear due to use.
Recommended leak test frequencies of three months are deemed to be adequate to detect seal degradation of resilient seals.
The three month test need not be conducted with the precision of the Type C 10CFR50, Appendix J criteria, however the test must be sufficient to detect degradation.
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- CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.3.1.2 Each isolation valve specified in Table 3.6-1 shall be l
demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by verifying that on a containment isolation test signal, each isolation valve actuates to its isolation position.
4.6.3.1.3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
4.6.3.1.4 Prior to exceeding conditions which require establishment of reactor building integrity per TS 3.6.1.1, the leak rate of the containment purge supply and exhaust isolation valves listed in Table 3.6-1 Part B shall be verified to be within acceptable limits per TS 4.6.1.2, unless the test has been successfully completed within the last three months.
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i ARKANSAS - UNIT 2 3/4 6-17
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