ML20043H462
| ML20043H462 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 06/19/1990 |
| From: | Maine Yankee |
| To: | |
| Shared Package | |
| ML20043H461 | List: |
| References | |
| NUDOCS 9006250440 | |
| Download: ML20043H462 (3) | |
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-ATTACHMENT B Proposed. Technical Specification Pages 3.'14-1 and 3.14-2 t
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3Il4 PRIMARY SYSTEM LEAKAGE Aeolicability:
Applies.to limiting operation of the plant under varying rates and conditions of primary system leakage.
Obiective:
E To specify primary plant operability with primary system leakage.
SDecification:
A.
When the reactor is above 2% power, two reactor coolant leak detection systems t
of different operating principles shall be operating, with one of the two-systems sensitive to radioactivity in the containment.
. Remedial Action:
If two reactor coolant leakage detection systems are operable but neither is sensitive to radioactivity, a system sensitive to radioactivity must be made operable within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
L B. The reactor coolant system indicated leak rate shall be limited to 1 gpm or less.
L Remedial Action:
If the indicated leak rate should exceed 1 gpm, within four I,
hours, investigate' the source and assess-safety implications, b
Reactor coolant system leakage shall not exceed any of the Specifications 1 C.
through-5 below.
1 l.
Leakage into the reactor containment of any magnitude that has been 1
determined to be an indication of a deterioration of primary system pressure boundary strength welds or material.
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,2.
Leakage into the reactor containment in excess of I gpm through bolted closures, valve packing, or other mechanical connections.
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Leakage in excess of I gpm that is unexplained or unaccounted for.
1 4.
Leakage in excess of-10 gpm to aerated or uncontained systems.
5.
Total primary-to-secondary leakage from any one steam generator
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shall not exceed 0.15 gpm.
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1 Remedial Actions:
'1 1.
If the leakage specified in C.1 aLove has been determined-to be a l
deterioration of primary system pressure boundary strength welds or i..
material, then the provisions of Specification 3.0.A.2 and 3 apply.
2.
If reactor coolant system leakage exceeds any of the Specifications C.2 through C.5 above, 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 />.
Amendment No. 38,53,65,68,91 3.14-1 01/29/86 CDF9053.LTR l
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Basis:
Reactor coolant system leakage may be indica'.ed by one or more of the following
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methods:
1.
Primary system water balance inventory.
2.
-Containment sump level.
3.
Containment air particulate monitor and/or radio gas monitor.
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Containment atmospheric humidity and/or air ejector effluent monitor.
5.
Steam generator blowdown monitor and/or air ejector effluent monitor.
Leakage may be indicated and/or identified by the following routine and special plant surveillance operations.
1.
Primary system hot leak test.
(Involves monitoring steady-state drop in Volume Control Tank Level).
2.
Direct observation from accessible locations within the containment.
3.
Sampling and analysis of containment atmosphere, steam generator blowdown-
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and air ejector effluent for radioactive and non-radioactive tracers.-
4.
Sampling and analysis of steam generator steam samples.
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. Reactor coolant system leakage will be maintained at the lowest practical value so that small leaks, with possible safety implications, will be more readily detected and identified.
A safety evaluation of a leak shall consider its magnitude,; nat_ure, and possible consequences.
It st 1 assure that off-site radiation exposure from the primary coolant system activny is within the guidelines of 10 CFR 20..
1 For the purposes of determining a maximum allowable secondary ~ coolant activity, the steam break accident is based on a postulated release of the contents of three steam, generators to the atmosphere using a site boundary dose limit of 1.5 rem.
The
~ limiting dose for this accident results from iodine in the secondary coolant. The-reactor coolant distribution of iodine isotopes with 1% failed fuel was used for this calculation.
I-131 is the dominant isotope because of its low MPC in air and because the other iodine isotopes have shorter halflives and therefore cannot build up to significant concentration in the secondary coolant, given the limitations on primary L
system leak rate and activity. The steam generators which operate at a constant programmed level contain 131m' of water at standard conditions. One tenth of the contained iodine is assumed:to reach the site boundary, making allowance for plate-out and retention in water droplets.
The maximum inhalation dose at the site boundary is then as follows:
Dose (rem) --(C) (V) IB(til (X/0) DCF) 10 3.14-2 CDF9053.LTR 1
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