ML19329A279
| ML19329A279 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/07/1978 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19329A276 | List: |
| References | |
| NUDOCS 8001020852 | |
| Download: ML19329A279 (7) | |
Text
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OCONEE TECHNICAL SPECIFICATIONS TO CONTROL WASTE WATER PONDS' RADI0 ACTIVITY 3.9.9 (a) The total quantity of radioactivity in the waste water / chemical treatment ponds (CTP) shall be limited to the quantities specified by the following expression:
.I AjQi 1 30_and, I BjQi 1 9 i
where:.Qj total quantity of radionuclide i in the CTP.in Ci
+
=
Ai -= conversion factor relating quantity of radionuclide i and the critical' organ dose commitment in mrem /Ci.
See Table 3.9.9-1.
Bj conversion factor relating quantity of radionuclide i
=
and the total body dose commitment in mrem /Ci.
See Table 3.9.9-1.
(b)
Discharge of resins from the secondary water clean-up system (SWCU) to the CTP shall not be allowed if noble-gases have been detected in the secondary system during their use.
. (c)' Samples of the resin from the SWCU shall be analyzed by gamma spectra analysis following each batch of' backwash.
A proportional composite sample of the resins and resin backwash water shall be analyzed quar-terly for P-32, Fe-55, Sr-89 and Sr-90.
Discharge of the resins from
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the SWCU to the CTP shall not be allowed if the radioactivity. of the previous batch of resin. backwash exceeded 0.01% of the limits of
- Specification' 3.9.9.a., i.e.,
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I AjQj 1.003 or
. IBjQj
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A cumulative inventory (decay corrected) or the total radio-3.9.10 activity by individudl nuclides discharged to the CTP shall be maintained and updated at least monthly.
Radioactivity input into the CTP shall be accounted for by:
(1) turbine building sump monitoring (Specification 3.9.11) and (2) separate samples of resin and resin backwash water from the secondary water clean-up system following each batch of backwash to the CTP (Specifi-cation 3.9.9(c)). A representative sample of the CTP water and basin bottoms shall be collected semi-annually and analyzed for P-32, Fe-55, Sr-89, Sr-90 and gamma isotopic.
The cummulative inventory, quantities discharged, and results of the sample analysis shall be reported in the semi-annual effluent report. A composite sample of the discharge from the oil collection basin shall be analyzed weekly by gama spectra analysis and quarterly for P-32, Fe-55, Sr-89 and Sr-90.
the results in terms of the total quantity of the individual radionuclides released to the environment shall be included in the semi-annual effluent report.
The turbine bui' ding sump shall be continuously monitored for radio-3.9.11 activity to a seasitivity of 1 x 10-6 pCi/ml water.
The monitor shall be set to alarm in the cor. trol room at a concentratior of greater than 5 x 10-6 uCi/ml.
The monitor shall be calibrated at least once per 18 months and a functional test daily. Wi;h the monitor inoperable and the turbine building sump operatino a i
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continuous discharge mode, representative grab samples will be-taken every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed for gross beta, gamma. With the. monitors' inoperable and the turbine building sump operating in a ~ batch discharge mode, a representative grab sample of the sump shall be analyzed for gross beta, ganma before discharge.
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ASSUMPTIONS IN CALCULATING DOSE TO A FROM RADI0 ACTIVITY RELEASES FROM THE C AT OCONEE-Oconee is from fish The dominant dose pathway for liquid effluents at This pathway is estimated to account an adult individual.
l The
_ ingestion tal body or critical organ dose of an individua.
I for 98% c i
ay alone is considered for determining limit ng fish ingestk...
The dose to the total body or radioactivity inventory in the CTP.
D, in mrem is calcu-organ j of an adult individual by the fish pathway, lated by:
1100fEjQijjjexp(-Ajt)
BD Dj
=
1 kg/yr; where U = usage factor for fish consumption, 2 3
1,100 ft /sec F = Flow rate of diluted effluent at water usage location 1100 = Factor to convert (Ci/yr)/(ft /sec) to pCi/ liter 3
d T, in Ci
-Qi = Release of nuclide i in time perio
/kg per pCi/ liter Bi_= Bioaccumulation factors for freshwater fish in p adults in mrem /pCi lDjj.= Ingestion dose factors fori, in hrs-l
.A1 = Decay constant of nuclide
~ fish, 24 hrs.
t = Delay time between harvest and consumption of
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i TABLE 3.9.9-1 FOR EXPRESSIONS LIMITING QUANTITY OF RADIONUCLIDES IN CTP
. FACTORS Radionuclide Ai Bi 2.0 E-5 2 0 E-5 H-3 3.8 E+2 1.49E+1 P-32 2.7 E-3 1.09E-5 Cr-51 1.2 E-1 7.32E-3 Mn-54 5.8 E-3 9.30E-4 Fe-55 7.1 E-2 8.21E-3 Fe-59 1.6 E-2 1.75E-3 C0 4.2 E-2 4.96E-3 j
C0-60 6.5 E-1 2.92E-1 I
Zn-65 8.5 E-1 3.98E-1 Rb-86 1.9 E-1 4.99E-3 Sr-89 4.8 E4 0 1.17E+0 Sr-90 4.0 E-2 1.96E-6 Y-91 2.1 E-3 4.53E-7 Zr-95 2.7 E-3 4.04E-9 Zr-97 1.3 E+1 1.17E-3 fib-95 2.1 E-3 1.70E.
Mo-99 4.5 E-3 1.67E-5 Ru-103 3.7 E-2 7.31E-5 Ru-106 6.3 E-2 9.23E-5 Ag-110m 9.2 E-2 2.99E-3 Te-125m 2.3 E-1 6.93E-3
. Te-127m 4.9 E-1 1.50E-2 Te-129m 4.2 E+0 3.38E-3 Te-131m-5.2 E-1 1.03E-2 Te-132 5.6 E-1 9.88E-4 I-1 31 5.1 E-2 1.07E-4 I-133 6.22E+0 5.08E+0 Cs-134 1.02E+0 7.38E-1
.Cs-136 4.58E+0 3.00E+0 ICs-137 1
TABLE 3.9.9-1 (Cont'd)_'_
i Radionuclide
- Ai Bi 4
Ba-140 -
3.3 E-3' l.06E-4 La-140 3.2 E-2 1.15E-7
'Ce-141 4.9 E-4 1.48E-8
-Ce-143 5.8 E-4 1.73E-9 Ce-144.
3.5 E 5.50E-7 1-
.tp-139 3.8 E-3 1.01E-8 f
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