ML20037A468

Proposed Tech Specs to Limit Primary & Secondary Coolant for Facility,Calculated by Accident Analysis Branch

ML20037A468
Person / Time
Site:	Oconee
Issue date:	01/29/1974
From:	US ATOMIC ENERGY COMMISSION (AEC)
To:
Shared Package
ML20037A467	List: ML20037A466 ML20037A468
References
NUDOCS 8002010285
Download: ML20037A468 (5)

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G OCONEE NUCLEAR STATION UNITS 2 AND 3 TECHNICAL SPECIFICATIONS The Technical' Specification activity limits on the primary and secondary coolant for the Oconce Nuclear Station Units 2 and 3 have been calcu-lated by the Accident Analysis Branch.

The primary coolant nobic gas and iodine activities are set by a pestulated tube rupture accident a-d the secondary iodine activity by a steam line break accident. A loss of off-site power is assumed to occur at the same time.

The Technical Specifications should read as follows:

1.

Maximum Reactor Coolant Activity.

Specification Thesg7eificactivityofthereactorcoolantduetodoseequivalent I-13L_ shall not exceed 2.0 pCi/ 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 during iodine transients.

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 tritium, with half-lives of more than 30 minutes shall not exceed 200/E pCi/ gram.

If the limits specified above are not satisfied, shutdown procedures shall be initiated immediately and the reactor shall be cooled to 500*F or less within eight hours after detection.

If the iodine activity exceeds the indicated maximum value the equilibrium iodine activity limit must be lowered by an amount proportionate to the amount by 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.

Sampling Frequency Whenever the reactor is critical, the sampling frequencies given in Table 4.2.1 shall be used to determine primariisnd secondary coolant Il ose equivalent I-131 concentration is defined as that cencentration D

of I-131 which alone would produce the same dose as the cuantity and isotopic mixture actually present.

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FIGURE 1 FRACTION (F) 0F DOSE EQUIVALENT I-131 PRIMARY COOLANT SPECIFIC ACIIVITY EQUILIBRIUM LIMITS j

WLLOWING POWER TRANSIENTS FOR OCONEE NUCLEAR STATION UNITS 2 6 3 (Maximum A11orable Concentration = F x Equilibrium Activity)

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I 20 30 40 50 60 70 80 90 100 Resulting Reactor Power After Power Transient

(% of Rated Power)

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activity Icvels.

In addition, the sampling progra a described in Tabic 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

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complete depressurization of the reactor coolant system; and (c) whenever the primary or secondary coolant activity exceeds the equilibrium limits specified above.

These tests shall be recorded together with the following inforrotion:

(a) 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, (b) fuel burnup by core region, (c) 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 /> prict to the first sample, and (d) history of de-gassing operations if any.

Reporting Requirements The above information shall be included in the semi-annual operating report.

If the limits of the specification are exceeded, a report shall be made to the Directorate of Licensing within 30 days.

TABLE 4.2.2 Sample _

Measurements Frequency Reactor Coolant Iodine activity, isotopic analysis Every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

• liquid sample including at least I-131, I-133, 1-135 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 following a steam generator tube rupture accident and a primary to secondary steam generator leakage of 1.0 gpm.

• In all cases, the minimum number of samples shall not be less than three for each transient.

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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.. Thirty minutes is the average. time'it takes the released gases to' reach the site boundary under adverse meteorological conditions and E is the average energy of~ betas and gammas per disintegration.

The' allowance to, exceed iodine equilibrium activity. limits during.the specified 48-hour periods following. initiation of. shutdown 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 at the site boundary of 30 rem during the 2-hour period following a= steam generator tube rupture accident.

In calculating the limits specified'above a'X/Q value of 2.3 x 10~4.sec/m3 and an iodine decontamination factor of 10 between the steam and. water phases were used.

2.

Secondary System Activity Specifications _

The specific activity of the secondary coolant due to dose equiva.

lent 1-131 shall not exceed 0.05 pCi/ 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 t'o.the thyroid at the site boundaryLof 1.5 rem during the 2-hour period following a main steam line break' accident._ This is alsoLbased 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.

In calculating the limits specified above a X/Q value of

~4 sec/m3 and an iodine decontamination factor of 10-2.3 x 10 between the' steam and water phases.in the unaffected steam generator.

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ITD1 1 of TABLE 4.2-1 FREQUENCIES FOR SAMPLING TESTS Maximum Time

.Between C_ heck Frequency Tests 1.

Reactor Coolant Cross Activity-3 Times / Week.(1)

-4 Days.

Liquid Samples' Isotopic analysis to determine equivalent.1-131 concentration Bi-weekly 15 Days R_adiochemical for

, (2)

E Determination Semi-annual-7 Months.

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 minimum of once each day.

( ) Redetermined if the primary coolant radioactivity changes by more than 10 pCi/cc in accordance with specification 3.1.D.

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