ML20117E675
| ML20117E675 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/19/1996 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20117E673 | List: |
| References | |
| NUDOCS 9609030028 | |
| Download: ML20117E675 (2) | |
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3/4.6 CONTAXNMENT SYSTEMS l
BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY l
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 accident analyses.
This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 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 accident analyses at the peak accident pressure, Pa. As an added conservatism, the measured overall integrated leakage rate is further limited to s0.75 L. or 50.75Lt (as applicable) during the performance of the periodic tests to account for possible degradation of the containment i
leakage barriers between leakage tests.
The surveillance testing for measuring leakage rates are consistent with the requirements of Appendix "J" of 10 CFR 50.
l 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 contaimment leak rate.
Surveillance testing of the air lock seals provide assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.
Action statement "a" has been modified by a note.
Note 2 allows use of the air lock for entry and exit for 7 days under administrative controls if both air j
locks have an inoperable door.
This 7 day restriction begins when the second air lock is discovered inoperable.
Containment entry may be required to perform Technical Specification (TS) surveillances and actions, as well as other activities on equipment inside containment that are required by TS or activities on equipment that support TS required equipment. An example of such an activity would be the isolation of a containment penetration by at least one OPERABLE valve, and the subsequent repair and post maintenance TS surveillance testing on the inoperable valve.
In addition, containment entry may be required to perform repairs on vital plant equipment, which if not repaired, could lead to a plant transient or reactor trip.
This note is not intended to preclude performing other activities (i.e., non-TS required activities or repairs on non-vital plant equipment) if the containment is entered, using the inoperable air lock, to perform an allowed activity listed above. This allowance is acceptable due to the low probability of an event that could pressurize the containment during the short time that the OPERABLE door is expected to be open.
For the purposes of this specification, the vertica'. end plates of the air lock barrel, on which the doors themselves are mounted, shall be considered part of the door.
9609030028 960819 PDR ADOCK 05000368 P
PDR ARKANSAS - UNIT 2 B 3/4 6-1 Amendment No.
i 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 releare of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses.
This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 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 accident analyses at the peak accident pressure, Pa. As an added conservatism, the measured overall integrated leakage rate is further limited to 50.75 La or 50 90L (as applicable) during the performance of t
the periodic tests to account for possible degradation of the contaimment leakage barriers between leakage tests.
The surveillance testing for measuring leakage rates are consistent with the requirements of Appendix "J" of 10 CFR 50.
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 testing of the air lock seals provide assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.
Action statement "a" has been modified by a note.
Note 2 allows use of the air lock for entry and exit for 7 days under administr&tive controls if both air locks have an inoperable door.
This 7 day restriction becins when the second air lock is discovered inoperable.
Containment entry may be required to perform Technical Specification (TS) surveillances and actions, as well as other activities on equipment inside containment that are required by TS or activities on eculpment that support TS reauired eouipment.
An example of such an activity would be the isolation of a containment penetration by at least one OPERABLE valve, and the subsecuent repair and post maintenance TS surveillance testino on the inoperable valve.
In addition, containment entry may be recuired to perform repairs on vital plant eauipment, which if not repaired, could lead to a plant transient or reactor trip.
This note is not intended to preclude performina other activities (i.e.,
non-TS required activities or repairs on non-vital plant equipment) if the containment is entered, usino the inoperable air lock, to perform an allowed activity listed above.
This allowance is acceptable due to the low probability of an event that could pressuriz,9 the containment durine the short time that the OPERABLE door is expected to be open.
For the purposes of this specification, the vertical end plates of the air lock l
barrel, on which the doors themselves are mounted, shall be considered part of the door.
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ARKANSAS - UNIT 2 B 3/4 6-1 Amendment No.
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