ML20126H914

Proposed Tech Specs,Incorporating Errata to Suppl 2 to Proposed Change 68 Re Radiological Environ Surveillance Program

ML20126H914
Person / Time
Site:	Maine Yankee
Issue date:	05/29/1985
From:	Maine Yankee
To:
Shared Package
ML20126H896	List: ML20126H894 ML20126H914
References
5745L-FWS, NUDOCS 8506100458
Download: ML20126H914 (4)

Text

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, ,,f s MAINE YANKEE ATOMIC POWER COMPANY 184 RADICLOGICAL-ENVI'R0t4 ENTAL; SURVEILLANCE PROGRAM ]~

'Applicabilith:/Thissectionappliesatalltimestoradiologicalenvironmental ]

surveillance and land use census.- ]

Objective: _To[verifythhtplant'operationshavenosignificantradiological

_ ].

effect on the environment and that continued operation will not ]

result in radiological effects detrimental to the environment. ]

The-program also shall verify that any measurable concentrations ]

of radioactive materials related to plant operations are not ]

-significantly higher than expected based on effluent measurements ]

and modeling of the environmental exposure pathways. ]

Specification: A'. : Radiological Environmental-Monitoring ]

~

1. The Radiological Environmental Monitoring Program shall ]

be conducted as specified in Table 4.8-1 with lower limits ]

of detection-(LLDs) as specified in Table 4.8-2. ]

2. With the Radiological Environmental Monitoring Program not ].

being conducted as specified in Table 4.8-1, prepare and ]

submit to the Commission, in'the Annual Radiological ]

Environmental Operating Report, a description or the ]

. reasons for not conducting the program as required and the ]

plans for preventing a recurrence. ] '

3. With the level of radioactivity in an environmental ]

sampling medium at a location specified in Table 4.8-1 ]

exceeding a reporting level of Table 4.8-3 when ]

averaged over any calendar quarter, prepare and submit ]

to the Commission with the'next Semi-Annual Effluent ]

Release Report following-receipt of the Laboratory ]

Analyses, a report which includes an evaluation of any ].

release conditions, environmental factors or other aspects =]

which caused the' limits of Table 4.8-3 to be exceeded.. ]

When more than one of the radionuclides in Table 4.8-3 ]- l are detected in the sampling medium, this report shall ]

be submitted if: ]

concentration (1) + concentration (2) + ...) 1.0 ))

~

reporting level (1) reporting level (2) ]

Exception: When radionuclides.Other than those in ]

Table 4.8-3. are detected and are the result of plant ]

effluents, this report shall be submitted if the -]

. potential annual dose to an individual is equal to ]

or-greater than the calendar.~ year limits of- ]-

Specifications 3.16.B.1, 3.17.B.1, and 3.17.C l. ]

f This' report is not required if the measured level ]

of radioactivity was not the result of plant .

]

effluents; however, in such an event, the condition ]

shall be reported and described in the Annual ]-

i Radiological Environmental Operating Report. ]

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4.8-1 _05/28/85 c

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. . MAINE YANKEE ATOMIC POWER COMPANY TAELE 4.8-2-(Continued) ]

TABLE NOTATION ]

a. The LLD is the smallest concentration of radioactive material in a sample ]

that will yield a net count, above system background, that will be_ detected ]

with 95% probability and that only a 5% probability exists of falsely ]

concluding that a blank observation represents a "real" signal. ]

For a particular measurement system (which may include radiochemical ]

separation): ]

LLD = 4.66

• Sb 3

]

E

• V

• 2.22

• Y _* Exp (-A *A t) ))

where ] l LLD is the "a priori" Lower Limit of Detection as defined above ]

(as picoeuries per unit mass or volume) ]

4.66 is a constant derived from the Kalpha and Kbeta values for ))

the 95% confidence level.. ]

Sb is the standard deviation of the background counting rate or of the ]

counting rate of a blank sample as appropriate (as counts per minute) ]

E is the counting efficiency (as counts per disintegration) -]

V-is' the sample size (in units of mass or volume) ]

2.22 is the number of disintegration per minute per picocurie ]

Y is the fractional radiochemical yield (2en applicable). ]

R is the radioactive decay constant for the particular ))

radionuclide ] 4 A t is the elapsed time between sample collection and analysis. ))

Typical values of E, V, Y, and A t can be used in the calculation. ))

This equation results in an LLO in terms of picocuries. For the purposes ]

of Specification 4.12,'where the required LLD is set forth in microcuries, ]

the terms 2.22 in the denominator should be replaced by 2.22E6 which is the ]

number of disintegrations per minute per microcurie. ]

lIn calculating the LLD for a radionuclide determined by gamma-ray ]

spectrometry, the background shall include the typical contributions of other ]

radionuclides normally present in the samples (e.g., Potassium-40 in milk ]

samples). ]

4.8-8 05/28/85 5745L-FWS J

-. . . . . MAINE YANKEE ATOMIC POWER COMPANY TABLE 4.12-1 ]

RADI0 ACTIVE LIQUID WASTE SAWLING AND ANALYSIS PROGRAM ]

Minimum . Lower Limit of ]

Sampling Analysis Type of Activity Detection (LLD) ]

Liquid Release Type Frequency Frequency Analysis- -(uC1/ml)a. ]

A. Batch Waste PR. PR Principal Gamma ~ 5 x 10-7 ]

Ralease Tanks d Each Batch Each Batch- Emitters f ]

I-131 1 x 10-6 ]

PR. M Dissolved and 1 x 10-5 ]

One Batch /M Entrained Gases ]

(Gamma Emitters) ]

PR MD H-3 1 x 10-5 ]

Each Batch Composite ]

Gross Alpha 1 x 10-7 ]

PR Q Sr-89 Sr-90 5 x 10-8 ]

Each Batch Co9posite b Fe-55 b 1 x 10-6 ))

B. Plant Continuous- Dc W PrincipapGamma 5 x 10-7 ]

e Composite b R31 eases Grab Sample

• Emitters ]'

on Turbine Building- W9 I-131 1 x 10-6 j Sump Grab Sample ** ]

oo Steam Generator M M Dissolved and 1 x 10-5 y Blowdown only Grab Sample Entrained Gases ]

W9 M H-3 1 x 10-5 ]

Grab Sample **- Compositeb Gross Alpha 1 x 10-7 ]

W9 . Q Sr-89, Sr-90 5 x 10-8 ]

Grab Sample ** . Compositeb ]

4.12-3 05/28/85

-5745L-FWS-

MAINE YANKEE ATOMIC POWER COMPANY The Radioactive Effluent Release Reports shall include a summary of ]

the quantities of radioactive liquid and gaseous effluents and solid ]

waste released from the unit with data summarized on a quarterly basis. ]

In addition, the Radioactive Effluent Release Report to be submitted ]

60 days after January 1 of each year shall include an annual summary of ] i hourly meteorological data collected over the previous year. This ]

annual summary may be either in the form of an hour-by-hour listing ]

on magnetic tape' of wind speed, wind direction, atmospheric stability, ]

and precipitation (if measured), or in the form of joint frequency ]

distributions of wind speed, wind direction, and atmospheric stability.* ]

The Radioactive Effluent Release Report to be submitted 60 days after ]

January 1 of each year shall also include an estimate of the maximum ]

potential radiation doses to the member (s) of the public from reactor .]

releases for the previous calendar year. The assessment of radiation ]

doses shall be performed in accordance with the Off-Site Dose ]

Calculation Manual (00CM). ]

The Radioactive Effluent Release Reports shall include the following ]

information for each class of solid waste (as defined by 10 CFR Part 61) ]

shipped off-site during the report period: ]

a. Container volume. ]

b. Total curie quantity (specify whether determined by measurement or ]

estimate). ]

c. Principal radionuclides (specify whether determined by measurement ]

or estimate). ]

d. Source waste and processing employed (e.g., dewatered spent resin, ]

compacted dry waste, evaporator bottoms). ]

e. Type of container (e.g., LSA, Type A, Type B, Large Quantity). ]

f. Solidification agent or absorbent (e.g., cement, asphalt, "Dow"). ]

The Radioactive Effluent Release Reports shall include a list and ]

description of unplanned releases from the site-to-site boundary of ]

, radioactive materials in gaseous and liquid effluents made during the ]

reporting period. ]

[ The Radioactive Effluent Release Reports shall include a listing of new ]

locations for dose calculations and/or environmental monitoring- ]

identified by the land use census pursuant to Specification 4.8.B. ]

The Radioactive Effluent Release Reports shall include changes to ))

the ODCM for information. ))

• 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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