ML19261E936
| ML19261E936 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/12/1973 |
| From: | Fontecilla H, Pasedag W US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19261E932 | List: |
| References | |
| NUDOCS 7910170990 | |
| Download: ML19261E936 (5) | |
Text
THREE MILE ISLAND NUCLEAR GENERATING STATION - UNIT 1 TECHNICAL, SPECIFICATIONS The Technical Specification activity limits on the primary and secondary coolant for Three Mile Island Nuclear Generating Station - Unit 1 have been calcu2ated by the Accident Analysis Branch. The primary coolant noble gas and iodine activities are set by a postulated tube rupture accident and the secondary iodine activity by a steam line break accident. A loss of offsite power is assumed to occur at the same time.
The Technical Specifications should read as follows:
1.
Maximut. Reactor Coolant Activity Specification The s ecific activity of the reactor coolant due to dose equivalent I-131_/ shall not exceed 0.5 uCi/ gram during equilibrium conditions or prior to startup. The iodine activity will be allowed to exceed the equilibrium limit but shall not exceed the maximum values in-dicated in Figure 1 during 48-hour periods following shutdown or power transients.2_/ Operation with a primary coolant activity higher than the equilibrium value, however, shall not exceed 5%
of the plant total yearly operating time. The total specific activity of the reactor coolant due to all nuclides, excluding trit _ium, with half-lives of more than 20 minutes shall not exceed 36/E uCi/ gram.
If the limits specified abose are not satisfied, shutdswn procedures shall be initiated within four hours and the reactor 6:all be cooled to 500*F or less within eight hours after detection.
If during a the leaine activity 48-hour period following a power transient exceeds the indicated maximum value the equilibrium iodine activity must be lowered by an amount proportionate to the amount by limit which the 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> limit was exceeded.
concentration I-131 concentration is defined as that Dose equivalent l_/
of I-131 which alone would produce the same dose as the quantity and isotopic mixture actually present.
is defined as a change in power exceeding 15 percent Power transient 1/
of rated power which occurs within a one hour period.
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Figure 1
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C 1483 267
. Samoling Frequency Whenever the reactor is critical, the sampling frequencie." given in Table 4.2.1 shall be used to determine primary and secondary coolant activity levels.
In addition, the sampling pregram described in Table 4.2.2 shall be initiated, (a) following a change in power exceeding 15 percent of rated power which occurs within one hour period; (b) during the first 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> following a partial or complete depressurization of the reactor coolant system; and (c) whenever the primary or secondary coolant activity exceeds the equiliot!un limits specified above.
These tests shall be recorded together with the following information:
Reactor power history, starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample Fuel burnup, by core region Clean-up flow history, starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sarple History of de-gassing operations, if any Reportine Recuirements The above information shall be included in the semi-annual operating If the limits of the specification are exceeded,. report report.
shall be made to the Directorate of Licensing within 30 day TABLE 4.2.2
?requency Measurements Samole Iodine activity, isotopic analysis Lvery 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
- Reactor Coolant liquid sample including at 1 cast I-131, I-133, I-135 than three
- In all cases, the minimum number of samples shall not be less for each transient.
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. Basis The basis for the primary coolant iodine activity limit is a computed dose to the thyroid at the site boundary of 1.5 rem during the 2-hour period folicwing a steam generator tube rupture accident and a primary to secondary steam generator leakage of 1.0 gpa.
The basis for the total activity limit is a computed whole body dose at the site boundary of 0.5 rem during the 2-hour period following a steam generator tube rupture accident.
Twenty minutes is the average time it takes the released gases to reach the site boundary under adverse meteoro-logical conditions and E is the average energy of betas and gammas per disintegration.
The allowance to exceed iodine equilibrium activity l!mits during the specified 48-hour periods following initiation of shutdowc or a power transient is made in order to account for possible iodine spiking phenomena.
The basis for the allowable maximum values is a resulting dose to the thyroid the site boundary of 30 rem during the 2-hour period following a steam at generator tube rupture accident.
4 sec/m3 In calculating the limits specified above a X/Q value of 9.0 x 10 was used.
- 2. Secondarv System Activity Specifications The specific activity of the secondary coolant due to dose equivalent I-131 shall not exceed 0.01 uCi/ gram.
If the limits specified above are not satisfied, shutdown procedures shall be initiated within four hours and the reactor shall be cooled to 500*F or less within eight hours after detection.
Basis The basis for this specified limit is a computed dose to the thyroid at the site boundary c f 1.5 rem during the 2-hour period following a main steam line break accident. This is also based on a primary to secondary steam generator leakage of 1.0 gpm.
No specifications are made in regard to noble gas activity because these gases are assumed to be continuously removed through the condenser.
4 sec/m3 In calculating the limits specified above a X/Q value of 9.0 x 10 was used.
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ITEM 1 of TABLE 4.1-2 FREOUENCIES FOR SA'4PLING TESTS Maximum Time Between Check Frecuency Tests
)
1.
Reactor Coolant Liquid Gross Activity 3 Times / Week 4 Days Sa=ples Isotopic analysis to de-termine equivalent Bi-weekly (3) 15 Days I-131 concentration Semiannual 7 Months Radiochemical for E Deteraination Tritium Activity Weekly 10 Days (1) When radioactivity level exceeds 25 percent of limits in specifications 3.1.D, the sampling frequency shall be increased to a ninimum of once each day.
(2) Redetermined if the primary coolant radioactivity changes by more than 10 LCi/cc in accordance with specification 3.1.D.
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