ML20126H914
| ML20126H914 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 05/29/1985 |
| From: | Maine Yankee |
| To: | |
| Shared Package | |
| ML20126H896 | List: |
| References | |
| 5745L-FWS, NUDOCS 8506100458 | |
| Download: ML20126H914 (4) | |
Text
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,,f MAINE YANKEE ATOMIC POWER COMPANY s
18 RADICLOGICAL-ENVI'R0t4 ENTAL; SURVEILLANCE PROGRAM
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4
'Applicabilith:/Thissectionappliesatalltimestoradiologicalenvironmental
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surveillance and land use census.-
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Objective:
_To[verifythhtplant'operationshavenosignificantradiological
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effect on the environment and that continued operation will not
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result in radiological effects detrimental to the environment.
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The-program also shall verify that any measurable concentrations
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of radioactive materials related to plant operations are not
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-significantly higher than expected based on effluent measurements
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and modeling of the environmental exposure pathways.
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Specification:
A'. : Radiological Environmental-Monitoring
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1.
The Radiological Environmental Monitoring Program shall
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be conducted as specified in Table 4.8-1 with lower limits ]
of detection-(LLDs) as specified in Table 4.8-2.
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2.
With the Radiological Environmental Monitoring Program not
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being conducted as specified in Table 4.8-1, prepare and
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submit to the Commission, in'the Annual Radiological
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Environmental Operating Report, a description or the
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. reasons for not conducting the program as required and the ]
plans for preventing a recurrence.
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3.
With the level of radioactivity in an environmental
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sampling medium at a location specified in Table 4.8-1
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exceeding a reporting level of Table 4.8-3 when
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averaged over any calendar quarter, prepare and submit
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to the Commission with the'next Semi-Annual Effluent
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Release Report following-receipt of the Laboratory
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Analyses, a report which includes an evaluation of any
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release conditions, environmental factors or other aspects =]
which caused the' limits of Table 4.8-3 to be exceeded..
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When more than one of the radionuclides in Table 4.8-3
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l are detected in the sampling medium, this report shall
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be submitted if:
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concentration (1)
+
concentration (2) +...) 1.0
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reporting level (1) reporting level (2)
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Exception: When radionuclides.Other than those in
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Table 4.8-3. are detected and are the result of plant
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effluents, this report shall be submitted if the
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. potential annual dose to an individual is equal to
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or-greater than the calendar.~ year limits of-
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Specifications 3.16.B.1, 3.17.B.1, and 3.17.C l.
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This' report is not required if the measured level
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f of radioactivity was not the result of plant.
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effluents; however, in such an event, the condition
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shall be reported and described in the Annual
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i Radiological Environmental Operating Report.
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nib f
9--
PDR __
P ~
4.8-1
_05/28/85 c
- 5745L-FWS
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MAINE YANKEE ATOMIC POWER COMPANY TAELE 4.8-2-(Continued)
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TABLE NOTATION
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a.
The LLD is the smallest concentration of radioactive material in a sample
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that will yield a net count, above system background, that will be_ detected
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with 95% probability and that only a 5% probability exists of falsely
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concluding that a blank observation represents a "real" signal.
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For a particular measurement system (which may include radiochemical
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separation):
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LLD =
4.66
- Sb 3
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E
- V
- 2.22
- Y _* Exp (-A *A t)
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where
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l LLD is the "a priori" Lower Limit of Detection as defined above
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(as picoeuries per unit mass or volume)
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and Kbeta values for
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4.66 is a constant derived from the Kalpha the 95% confidence level..
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Sb is the standard deviation of the background counting rate or of the
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counting rate of a blank sample as appropriate (as counts per minute)
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E is the counting efficiency (as counts per disintegration)
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V-is' the sample size (in units of mass or volume)
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2.22 is the number of disintegration per minute per picocurie
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Y is the fractional radiochemical yield (2en applicable).
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R is the radioactive decay constant for the particular
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radionuclide
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4 A t is the elapsed time between sample collection and analysis.
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Typical values of E, V, Y, and A t can be used in the calculation.
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This equation results in an LLO in terms of picocuries. For the purposes
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of Specification 4.12,'where the required LLD is set forth in microcuries,
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the terms 2.22 in the denominator should be replaced by 2.22E6 which is the
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number of disintegrations per minute per microcurie.
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lIn calculating the LLD for a radionuclide determined by gamma-ray
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spectrometry, the background shall include the typical contributions of other
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radionuclides normally present in the samples (e.g., Potassium-40 in milk
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samples).
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4.8-8 05/28/85 5745L-FWS J
MAINE YANKEE ATOMIC POWER COMPANY TABLE 4.12-1
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RADI0 ACTIVE LIQUID WASTE SAWLING AND ANALYSIS PROGRAM
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Minimum Lower Limit of
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Sampling Analysis Type of Activity Detection (LLD)
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Liquid Release Type Frequency Frequency Analysis-
-(uC1/ml)a.
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A.
Batch Waste PR.
PR Principal Gamma ~
5 x 10-7
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d Ralease Tanks Each Batch Each Batch-Emitters f
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I-131 1 x 10-6
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PR.
M Dissolved and 1 x 10-5
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One Batch /M Entrained Gases
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(Gamma Emitters)
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D H-3 1 x 10-5
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PR M
Each Batch Composite
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Gross Alpha 1 x 10-7
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PR Q
Sr-89 Sr-90 5 x 10-8
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b 1 x 10-6
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b Fe-55 Each Batch Co9posite e
b PrincipapGamma 5 x 10-7
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B.
Plant Continuous-Dc W
R31 eases Grab Sample
- Composite Emitters
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on Turbine Building-W9 I-131 1 x 10-6 j
Sump Grab Sample **
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oo Steam Generator M
M Dissolved and 1 x 10-5 y
Blowdown only Grab Sample Entrained Gases
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W9 M
H-3 1 x 10-5
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Grab Sample **- Compositeb Gross Alpha 1 x 10-7
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W9 Q
Sr-89, Sr-90 5 x 10-8
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b Grab Sample **. Composite
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4.12-3 05/28/85
-5745L-FWS-
MAINE YANKEE ATOMIC POWER COMPANY The Radioactive Effluent Release Reports shall include a summary of
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the quantities of radioactive liquid and gaseous effluents and solid
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waste released from the unit with data summarized on a quarterly basis.
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In addition, the Radioactive Effluent Release Report to be submitted
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60 days after January 1 of each year shall include an annual summary of
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i hourly meteorological data collected over the previous year. This
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annual summary may be either in the form of an hour-by-hour listing
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on magnetic tape' of wind speed, wind direction, atmospheric stability,
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and precipitation (if measured), or in the form of joint frequency
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distributions of wind speed, wind direction, and atmospheric stability.*
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The Radioactive Effluent Release Report to be submitted 60 days after
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January 1 of each year shall also include an estimate of the maximum
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potential radiation doses to the member (s) of the public from reactor
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releases for the previous calendar year. The assessment of radiation
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doses shall be performed in accordance with the Off-Site Dose
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Calculation Manual (00CM).
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The Radioactive Effluent Release Reports shall include the following
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information for each class of solid waste (as defined by 10 CFR Part 61)
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shipped off-site during the report period:
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a.
Container volume.
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b.
Total curie quantity (specify whether determined by measurement or
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estimate).
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c.
Principal radionuclides (specify whether determined by measurement
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or estimate).
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d.
Source waste and processing employed (e.g., dewatered spent resin,
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compacted dry waste, evaporator bottoms).
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e.
Type of container (e.g., LSA, Type A, Type B, Large Quantity).
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f.
Solidification agent or absorbent (e.g., cement, asphalt, "Dow").
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The Radioactive Effluent Release Reports shall include a list and
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description of unplanned releases from the site-to-site boundary of
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radioactive materials in gaseous and liquid effluents made during the
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reporting period.
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The Radioactive Effluent Release Reports shall include a listing of new
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locations for dose calculations and/or environmental monitoring-
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identified by the land use census pursuant to Specification 4.8.B.
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The Radioactive Effluent Release Reports shall include changes to
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the ODCM for information.
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In lieu of submission with the first half year Radioactive Effluent Release Report, the Licensee has the options of retaining this summary of required meteorological data in a file that shall be provided to the NRC upon request.
5.9-3 05/28/85 5745L-FWS
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