ML20107H524

Revised Radiological Effluent Tech Spec Pages 21,22,23,26 & 27 Re Sampling & Analysis of Incinerated Oil

ML20107H524
Person / Time
Site:	FitzPatrick
Issue date:	02/19/1985
From:	POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20107H516	List: ML20107H513 ML20107H524
References
NUDOCS 8502270181
Download: ML20107H524 (5)

Text

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TABLE 3.2-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detection Gaseous Release Sampling Analysis Type of Activity (LLD)(a)

Type Frequency Frequency Analysis (uCi/ml)

-4 Main Stack and Monthly Monthly Principal Gamma 1 x 10 Refuel Floor Vent Grab Noble Emitters (b) and Sample Gases Reactor Building

-6 Vent and Quarterly Quarterly H-3 1 x 10 Turbine Building Grab Sample Vent and Radwaste Building Continuous (c) Weekly I-131 1 x 10 -12 Vent Charcoal Sample * '

Continuous (c) Weekly Principal Gamma 1 x 10 -11 Particulate Emitters Sample * *

(I-131, others)

-11 Continuous (") 1 Wk/Mo Gross Alpha 1 x 10 Particulate Sample

-I1 Continuous (c) 4 Wk/Qr Sr-89, Sr-90 1 x 10 Composite Particulate Sample

-5 Continuous (c) Noble Gas Noble Gases 1 x 10 Monitor Gross Beta or Gamma Incinerated Prior Each Principal Gamma 5 x 10-

}

011(8 to Each Batch Emitters

-6 Batch I-131 1 x 10 B502270181 850219 PDR ADOCK 05000333 p

PDR Amendment No.

21

NOTES FOR TABLE 3.2-1 (a) The LLD is defined, for purpose of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probabil-ity and with only 5% probability of falsely concluding that a blank ob-servation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 sb LLD

=

0 E

V 2.22 x 10 + Y + exp (-Aat)

Where:

LLD is the a priori Iower limit of detection, as defined above (in micro-curies per unit mass or volume);

s is the standard deviation of the background counting rate or of the b

counting rate of a blank sample, as appropriate (in counts per minute);

E is the counting efficiency (in counts per disintegration);

V is the sample size (in units of mass or volume);

0 2.22 x 10 is the number of disintegrations per minute per microcurie; Y is the fractional radiochemical yield (when applicable);

A is the radioactive decay constant for the particular radionuclide; and at for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.

Typical values of E, V, Y, and At should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

(b) The principal gamma emitters for which the LLD specification applies ex-clusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-135m, and Xe-138 for gaseous emissions; and, Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, and Cs-137 for particulate emissions.

This list does not mean that only these nuclides are to be detected and reported.

Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported in the Semiannual Radioactive Effluent Release Report.

The LLD for Mo-99, Ce-141, and Ce-144 is 5x10 II.

For oil samples, Table 2.2-1, Note (c) applies.

(c) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calcula-tion made in accordance with Specifications. This determination shall be made using design flow rates if flow meters are not provided or are inoperable.

Amendment No.

22

e*

i NOTES FOR TABLE 3.2-1 (continued)

(d) Main stack sampling and analysis shall also be performed following shut-down, start-up, or a thermal power change exceeding 20% of rated thermal power in one hour. This requirement applies only if:

(1) analysis shows that the dose equivalent I-131 concentration in the primary coolant has increased more than a factor of 3; and (2) the noble gas activity monitor shows that effluent activity has increased by more than a factor of 3 after correcting for increases due to changes in thermal power level in both cases.

(e) When the offgas filter system charcoal absorbers are not in service, main stack samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler.

In addition, sampling shall be performed following each shut-down, start-up or thermal power change exceeding 20% of rated thermal power in one hour.

In those instances, campling shall be performed at least daily until two consecutive samples show no increase in concentra-tion but in no case for more than 7 consecutive days.

This requirement applies only if:

(1) analysis shows that the dose equivalent I-131 con-centration in the primary coolant has increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has increased more than a factor of 3 after correcting for increases due to changes in thermal power level in both cases.

Analysis of daily samples shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing.

When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10.

(f) When the offgas filter system charcoal absorbers are in service, main stack samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler.

In addition, sampling shall be performed following each shut-down and start-up.

In those instances, sampling shall be performed at least daily until two consecutive samples show no increase in concentra-tion but in no case for more than 7 consecutive days.

This requirement applies only if: (1) analysis shows that the dose equivalent I-131 con-centration in the primary coolant has increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has increased more than a factor of 3 after correcting for increases due to changes in thermal power level in both cases.

Analysis of daily samples shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing.

When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10.

(g) Incinerated oil may be discharged via points other than the main stack and building vents (i.e., auxiliary boiler).

Release shall be accounted for based on pre-release grab sample data.

(h) Samples for incinerated oil releases shall be collected from and repre-sentative of filtered oil in liquid form. Whenever oil samples cannot be filtered such as No. 6 bunker fuel oil, raw oil samples shall be col-f lected and analyzed.

Amendment No.

23 I

I

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.4 DOSE DUE TO 10 DINE-131, IODINE-133. TRITIUM AND 3.4 DOSE DUE TO IODINE-131, 10 DINE-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM RADIONUCLIDES IN PARTICULATE-FORM Applicability Applicability Applies to the cumulative dose from Iodine-131, Applies to the calculation of the dose due to Iodine-133 Tritium, and radionuclides in par-Iodine-131 Iodine-133 Tritium, and radionu-ticulate form in gaseous effluents.

clides in particulate form in gaseous efflu-ents.

Objective Objective To assure that the dose l' ultations of 10 CFR To ensure that appropriate calculations are 50, Appendix I, are met, performed to determine the dose from 10-dine-131, Iodine-133, Tritium, and radionu-clides in particulate form.

Specifications Specifications

a. The dose to a member of the public at or

a. Cumulative dose contributions shall be cal-beyond the site boundary from Iodine-131, culated at least monthly in accordance with Iodine-133, Tritium, and radionuclides in the ODCM for the current calendar quarter particulate form with half-lives greater and the current calendar year.

than 8 days released from the plant in gaseous effluents shall be limited:

1. During any calendar quarter to less than or equal to 7.5 mrem to any organ; and,

2. During any calendar year to less than or equal to 15 mrem to any organ.

3. Less than 0.1% of the limits of Specift-cation 3.4.a.1 and 3.4.a.2 as a result of burning contaminated oil.

Amendment No.

26

- s

.' ?. -

LIMITING' CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS-b..With the calculated dose from the release of Iodine-131, Iodine-133, Tritium, and. radio-nuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, ' prepare and submit to the Commission within 30 days a report that:

1. Identifies the cause(s) for exceeding the limit; and

2. Defines the corrective actions that have been taken to reduce the releases; and

3. Identifies the proposed corrective ac-tions to be taken to assure that subse-

_quent releases will be in compliance with the above. limits.

i Amendment No.

27