ML20128Q230
| ML20128Q230 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 10/16/1996 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20128Q226 | List: |
| References | |
| NUDOCS 9610180285 | |
| Download: ML20128Q230 (6) | |
Text
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NPF-38-182 ATTACHMENT A 9610180285 961016ADOCK 05000382 PDR PDR p
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CONTAINMENT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) a.
Type A tests shall be conducted in accordance with tha schedule and criteria specified in 10 CFR 50, Appendix J, as modified by approved exemptions.
b.
Type B and C tests shall be conducted with gas at P,, 44 psig, at intervals no greater than 24 months except for tests involving:
1.
Air locks, 2.
Purge supply and exhaust isolation valves with resilient material seals.
WATERFORD - UNIT 3 3/4 6-3 AMINDMENT NO. 4 85,110 7
3/4.6 CONTAINMENT SYSTEMS I
BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAIPNENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in :he safety analyses.
This restriction, in conjunction with the leakage rate limitation, will limit the SITE BOUNDARY radiation doses to within the limits of 10 CFR Part 100 during accident conditions.
3/4.6.1.2 CONTAINMENT LEAKAGE l
The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the safety analys9s at the peak accident pressure, P measured overall integrated leakage rate l. As an added conservatism, the s further limited to less than or equal to 0.75 L or 1r" than or eaual to 0.75 L as applicable during performance of lhe pei tadic tests to account for,,possible degradation of the containment leakage barriers between leakage tests.
The surveillance requirements for measuring leakage rates are consistent with the requirements of 10 CFR 50, Appendix J and performed in accordance with the methods and provisions of ANSI N45.4-1972.
Secondary containment bypass leakage paths previously, Table 3.6-1, have been incorporated into plant procedure UNT-005.026.
3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate.
Surveillance testina cf the air lock s6als provides assurance that the overall air lock leakags will not become excessive due to seal damage during the intervals between air lock leakage tests.
WATERFORD - UNIT 3 8 3/4 6-1 AMENDMENT NO. 4-66,110
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NPF-38-182 ATTACHMENT B
GONTAINMENT SYSTEMS SURVEILLANCE Requirements (Continued) a.
Type A tests shall be conducted in accordance with the schedule and criteria specified in 10 CFR 50, Appendix J, Option B, as modified by l
approved exemptions.
b.
Type B and C tests shall be conducted with gas at P,44 psig, at intervals no greater than 24 months except for tests involving:
1.
Air locks, 2.
Purge supply and exhaust isolation valves with resilient material seals.
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l WATERFORD - UNIT 3 3/4 6-3 AMENDMENT NO. 4,85,440
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- 3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses. This restriction, in conjunction with the leakage rate limitation, will limit the SITE BOUNDARY radiation doses to within the limits of 10 CFR Part 100 during accident conditions.
3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the safety analyses at the peak accident pressure, Pa. As an added conservatism, the measured overallintegrated leakage rate is further limited to less than or equal to 0.75 La or less than or equal to 0.75 Lt, as applicable during performance of the periodic tests to account for possible degradation of the containment leakage barriers between leakage tests.
The surveillance requirements for measuring leakage rates are consistent with the requirements of 10 CFR 50, Appendix J, and performed in accordance with the methods and provisions of ANSI N45.4-1972. Periodicity for Type A testing is determined by the performance-based leakage-testing program.
Secondary containment bypass leakage paths, Table 3.6-1, has been relocated into the Technical Requirements Manual.
3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and co ltainment leak rate.
Surveillance testing of the air lock seals provides amurance thz t the overall air lock leakage will not become excessive due to seal damage during r.he intervals between air lock leakage tests.
WATERFORD < UNIT 3 B 3/4 6-1 AMENDMENT NO. 74, 85,440 l