ML20071E726
| ML20071E726 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 03/09/1983 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20071E711 | List: |
| References | |
| TAC-46694, TAC-46695, NUDOCS 8303150338 | |
| Download: ML20071E726 (7) | |
Text
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Dose Equivalent I-131 Dose Equivalent I-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present.
The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power l
and Test Reactor Sites."
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5 - Average Disintegration Energy 5 shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for iso-
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topes, other than iodines, with half lives greater than 15 minutes, making up at least 95% of the total non-iodine activity in the coolant.
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i 8303150338 830309 PDR ADOCK 05000266 15.1-6 P
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MAXIMUM COOLANT ACTIVITY Specification:
The specific activity of the reactor coolant shall be limited to:
1.
Less than or equal to 1.0 microcurie per gram Dose Equivalent I-131.
a.
If the specific activity of the reactor coolant is greater than 1.0 microcurie per gram Dose Equivalent I-131 but within the allowable limit (below and to the left of the line) shown on Figure 15.3.1-5, operation may continue for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided that the cumulative operating time under these circumstances does not exceed 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in any consecutive 12-month period.
Reactor Coolant Sampling shall'be in accordance with Table 15.4.1-2.
b.
If the specific activity of the reactor coolant is greater than 1.0 microcurie per gram Dose Equivalent I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeds the allowable limit (above and to the right of the line) shown on Figure 15.3.1-5, the reactor will be shutdown and the average reactor coolant temperature will be less than 500*F within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
2.
Less than or equal to 100/5 microcuries per gram.
4 If the specific activity of the reactor coolant is greater than 100/5 a.
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i microcuries per gram, the reactor will be shutdown and the average reactor coolant temperature will be less than 500*F within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
Reactor Coolant Sampling shall be in accordance with Table 15.4.1-2.
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Basis 1
The limitations on the specific activity of the reactor coolant ensure that the resulting 2-hour doses at the site boundary will not exceed and appropriately small fraction of Part 100 limits following a steam generator tube rupture 1
accident in conjunction with an assumed steady state primary-to-secondary steam generator leakage rate of 1.0 GPM.
The values for the limits on specific activity represent limits based upon a parametric evaluation by the NRC of typical site locations.
These values are conservative for Point Beach Nuclear Plant.
Continued power operation for limited time periods with the reactor coolant's specific activity greater than 1.0 microcurie / gram Dose Equivalent I-131, but within the allowable limit shown on Figure 15.3.1-5, accommodates possible iodine spiking phenomenon which may occur following changes in thermal power.
Operation with specific activity levels exceeding 1.0 microcurie / gram Dose Equivalent I-131 but within the limits shown on Figure 15.3.1-5 increase the f
f 2-hour thyroid dose at the site boundary by a factor of up to 20 following a l
postulated steam generator tube rupture.
Reducing T,yg to less than 500*F normally prevents the release of activity should a steam generator tube rupture since the saturation pressure of the reactor coolant is below the lift pressure of the atmospheric steam relief l
valves.
The surveillance requirements provide adequate assurance that exces-I 15.3.1-10 j
sive specific activity levels in the primary coolant will be detected in suffi-cient time to take corrective action.
A reduction in frequency of isotopic analyses following power changes may be permissible if justified by the data obtained.
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o 20 30 40 so so 70 so 90 100 PERCENT OF RATED THERMAL POWER DOSE EQUlVALENT l-131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity >1.0 Ci/ gram Dose Equivalent 1-131 9
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TABLE 15.4.1-2 MINIMUM FREQUENCIES FOR EQUIPMENT AND SAMPLING TESTS Test Requency 1.
Reactor Coolant Samples Gross Beta gamma 5/ week (7) activity (excluding tritium)
Tritium activity Monthly Radiochemical 5 Semiannually (2)
Determination Isotopic Analysis for Every two weeks (1)
Dose EQUIVALENT I-131 Concentration Isotopic Analysis for a) Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Iodine including I-131, whenever the specific,
I-133, and I-135 activity exceeds 1.04Vgram Dose _ Equivalent (g131or 100/E mci / gram.
b.) One sample between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following a thermal power change exceeding 15% of rate power in a one-hour period.
Chloride Concentration 5/ week (8)
Diss. Oxygen Conc.
5/ week (6)
Flouride Conc.
Weekly
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Reactor Coolant Boron Baron Concentration Twice/ week 3.
Refueling Water Storage Boron Concentration Weekly (6)
Tank Water Sample 4.
Boric Acid Tanks Boron Concentration Twice/ week 5.
Spray Additive Tank Na0H Concentration Monthly l
6.
Accumulator Boron Concentration Monthly 7.
Spent Fuel Pit Boron Concentration Monthly 8.
Secondary Coolant Gross Beta gama Activ-Weekly (0}
ity or gamma isotopic t
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TABLE 15.4.1-2 (Continued)
Test Frequency 24.
Integrity of Post Accident Evaluate Yearly Recovery Systems Outside Containment I')
25.
Containment Purge Supply Verify valves are Monthly and Exhaust Isolation Valves locked closed (1) Required only during periods of power operation.
(2) E determination will be started when the gross activity analysis of a fil-tered sample indicates > 10pc/cc and will be redetermined if the primary coolant gross radioactivity of a filtered sample increases by more than 10 pc/cc.
(3) Drop tests shall be conducted at rated reactor coolant flow.
Rods shall be dropped under both cold and hot conditions, but cold drop tests need not be timed.
(4) Drop tests will be conducted in the hot condition for rods on which mainten-ance was performed.
(5) As accessible without disassembly of rotor.
(6) Not required during periods of refueling shutdown.
(7) At least once per week during periods of refueling shutdown.
(8) At least three times per week (with maximum time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> between samples) during periods of refueling shutdown.
(9) Not required during periods of cold or refueling shutdown.
(10) During end-of-cycle period of operation when boron concentration is less than 100 ppm, this test may be waived due to operational limitations.
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