ML19327B445
| ML19327B445 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/19/1989 |
| From: | ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19327B444 | List: |
| References | |
| NUDOCS 8910310209 | |
| Download: ML19327B445 (3) | |
Text
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3.1.6 Leakege
Specification c
3.1.6.1 If the total reactor coolant leakage rate exceeds 10 gpm, the reactor shall be shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of detection.
3.1.6.2 If unidentified reactor coolant leakage (exceeding normal evaporative losses) exceeds 1 gpm or if any reactor coolant leakage is evaluated as unsafe, the reactor shall be shut-down within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of detection.
3.1.6.3.a If it is determined that any reactor coolant leakage exists through a non-isolable fault in a reactor coolant system strength boundary (such as the reactor ves'iel, piping, valve body, etc., except steam generator tubes), the reactor shall be shutdown and a cooldown to thc cold shutdown condition shall be initiated withir. I4 hours of dete: tion.
3.1.6.3.b If the leakage through the tubes of any one steam generator equals or exceeds 500 gallons per day (0.347 gpm), a reactor shutdown shall'be initiated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and the reactor shall be in the cold shutdown condition within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
3.1.6.4 Deleted 3.1.6.5 Action to evaluate the safety implication of reactor coolant leakage shall be initiated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of detection.
The nature, as well as the magnitude of the leak, shall be considered in this evaluation.
The safety evaluation shall assure that the exposure of offsite personnel to radiation is l
within the guidelines of 10CFR20.
3.1.6.G If reactor shutdown is required per Specification 3.1.6.1, 3.1.6.2, or 3.1.6.3 the reactor shall not be restarted until the leak is repaired or until the problem is otherwise corrected.
3.1.6.7 When the reactor is at power operation, three reactor cool-ant leak detection systems of different operating principles i
shall be in operation.
One of these systems is sensitive to radioactivity and consists of a radioactive gas detector and an air particulate activity detector.
Both of these instru-r ments may be out-of-service simultaneously for a period of no more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided two other means are available to detect leakage and reactor building air samples are taken and analyzed in the laboratory at least once per shif t; other-wise, be in at least Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and I
in Cold Shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
3.1.6.8 Loss of reactor coolant through reactor coolant pump seals anti system valves to connecting systems which Amendment No. 57, II5, 128 27 4
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'f NOTES:
(1)- In all inspectisns, previously degraded tubes whose degradations have not been spanned by a sleeve must exhibit significant (>10%) further wall penetrations to 1
be included-in the above percentage calculations.
L-(2) Where special inspections are performed pursuant to L
4.18.3.a.3, defective or degraded tubes found as a I
result of the inspection shall be included in
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determining the. Inspection Results Category for that-special inspection but need not be included in detecmining the Inspection Results Category for the general steam generator inspection.
i 4.18.4 Inspection Intervals The above-required inservice inspections of steam generator tubes shall be performed at the following frequencies:
a.
The baseline inspection shall be performed during the first refueling shutdown.
Subsequent inservice inspections shall be performed at intervals of not less than 10 nor more than 24 calendar months after the previous inspection.
If the results of two consecutive inspections for a piven group
- of tubes following service under all volatile treatment (AVT) conditions fall into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval for that group may be extended to a maximum of 40 months.
b.
If the results of the inservice inspection of a steam generator performed in accordance with Table 4.18.2 at 40-month intervals for a given group
- of tubes fall in Category C-3, subsequent inservice inspecties shall be performed at intervals of not less than 10 nor more than 20 calendar months after the previcus inspection.
The increase in inspection frequency shall apply until a subsequent inspection meets the conditions specified in 4.18.4.a and the interval can be extended to 40 months.
c.
Additional unscheduled inservice inspections shall be performed on l-each steam generator in accordance with the first sample L
inspection specified in Table 4.18.2 during the shutdown i
subsequent to any of the following conditions:
l 1.
Primary-to-secondary leakage in excess of the limits of Specification 3.1.6.3.b (Inservice inspection not required if leaks originate from tube-to-tubesheet welds.
For leakage originating in the lane or wedge regions, a 100% inspection of the affected region may be performed in lieu of the first l-sample inspection specified in Table 4.18.2).
2.
A seismic occurrence greater than the Operating Basis Earthquake,
- A group of tubes means: (a) All tubes inspected pursuant to 4.18.3.a.3, or (b) All tubes in a steam generator less those inspected pursuant to 4.18.3.a.3.
Amendment No. 24, 41, 86, 106 1101
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