ML20024G957
| ML20024G957 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 12/03/1973 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20024G562 | List: |
| References | |
| NUDOCS 9105020328 | |
| Download: ML20024G957 (2) | |
Text
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3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILIANCE REQUIREMENTS E.
Feactor BuiMing Ventilation Isolation and St andby Gas Treatment System Initiation 1.
n.
Except as specified in 3.2.E.1.b
/
below, four radiation monitors shall be operable at all times.
b.
One of the two monitors in the venti-lation plenum and one of the two radia-l tion monitors on the refueling floor may be inoperable for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
If the l
inoperable monitors are not restored to l
service in this time, the reactor build-ing ventilation system shall be iso-l lated and the standby gas treatment system operated until repairs are complete.
2.
The radiation monitors shall be set to trip as follows:
O (a) ventilation plenum i 3 mr/hr (b) refueling floor 6100 mr/hr 3.
When irradiated fuel is in the reactor vessel and the reactor water temperature is above 212 F, the limiting conditions for operation 0
for the instrumentation listed in Table 3.2.4 shall be met.
9105020328 731203 PDR ADOCK 05000263 P
PDR 49 3.2./4.2 REV (11/15/73)
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Ea c.A batch to be released will conform to 10 CFR Part 20 release limits on an instantaneous basis, i.e.,
annua? averaging will not be used as perndtted by 10 CFR Part 20.
See Section 9.2.3 of the FSAR. The radio-activity level in the discharge canal for a given release of waste will be the highest when the discharge canal flow is lowest.
This occurs during " closed cycle" cooling tower operation at which time the cooling tower blowdown of approximately 36 cubic feet per second is the major flow in the discharge canal. - The i
rate of pumping the radwaste effluent into the discharge canal is variable and can, therefore, be controlled to maintain the concentration within the specified'11mit. This type of operation will be employed only when the river flow is very low and will result in further dilution between discharge canal effluent and the river.
D.
Railoactive Liquid Storage The waste sample, floor drain sample, waste surge, and condensate storage tanks are not contained in a Class I structure. The maximum gross radioactivity in liquid storage in the specified tanks has been limited on the basis of an accidental spill from all stated tanks due to a seismic event great enough to damage them.
3 Assuming a low recorded river flow of 1000 ft /sec, a day period over which the radioactive liquid wastes are diluted in the river, and consumption of the water by individuals at standard man consumption t
rate (3000 ml/ day), the single intake by an individual would not exceed one-third the yearly intake allowable
- by 10 CFR Part 20 for unidentified radioisotopes (1 x 10-7 uCi/ml). The factor of 3 was applied to 10 CFR Part 20 limits as recommended for situations in which population groups could be exposed.
The sampling frequency has been established so that if the maximum amount of gress radioactivity is exceeded, action can be taken to reduce the radioactivity to a level below the specified limit.
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E.
Augmented Off-Gas System i
i The hydrogen monitors are used' to detect possible hydrogen buildups which could result in a possible hydrogen api i
explosion.
Isolation of the off-gas flow would prevent the hydrogen explo,sion and possible damage to the augmented of f-gas system.
h Experience has shown that a daily check with monthly testing and quarterly calibration assures proper operation of the hydrogen monitors and quarterly calibration assures proper operation of the radiation monitors.
i The maximum gross radioactivity in one gas decay tank. has been limited on the basis that accidental release i
of.its contents to the environs by operator error af ter 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> decay should not result in exceeding the dose equivalent to the maximum quarterly release rate specified in Specification 3.8.A.2.
Staff analysis of an elevated release under accident meteorology for a minimum _ release period of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> indicated a release of 22,000 curies of Xe-133 or the dose equivalent would result in a whole body dose of 20 mrem at the nearest site boundary 179A REV (11/15/73)
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