ML20236M162

Radiological Environ Monitoring Program for TMI-1

ML20236M162
Person / Time
Site:	Three Mile Island
Issue date:	11/09/1987
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20236M147	List: ML20236M144 ML20236M151 ML20236M162 ML20236M205
References
PROC-871109, NUDOCS 8711120113
Download: ML20236M162 (17)

Text

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THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.

i FOR THE THREE MILE ISLAND NUCLEAR POWER STATION UNIT 1 -l L

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I

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l INTRODUCTION j The RADIOLOGICAL ENVIRONMENTAL ~ MONITORING PROGRAM incorporates: the procedure's . -

for the Conditions for Operation and the Monitoring Requirements for the j monitoring program. This program is required by Technical Specification 6.15

. 't and is applicable at all times.: Changes to this program must be reviewed by

. the NRC as: required by Technical Specification 6.15.

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-3' CONTENTS-1 PAGEL

!I .I. CONDITIONS FOR' OPERATION 1

1. Monitoring Program ': 11

2. . Land-Use Census .7 i

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- 3'. Inte'rlaboratory Comparison Program . l'0 '-

II. MONITORING REQUIREMENTS 11.

1. Sampling and- Analysis Methods .

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2. Land Use Census Methods 11 -

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3. Interlaboratory Comparison Progam 11. i 1

I l TABLES .

1 Sample Location and Frequency 3 Reporting Levels for Radioactivity Concentrations '

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in Environmental Samples i

3 Detection Capabilities for Environmental Sample Analyses Lower Level of Detection 12 1 j

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I. CONDITIONS FOR OPERATION

, 1. Monitoring Program l The radiological environmental monitoring program shall be conducted I as specified in Table 1. This program is applicable at all times.

Changes to this program must be reviewed by the NRC hs required by Technical Specification 6.15.

The radiological monitoring program provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of members of the public resulting from the station operation. This monitoring program thereby implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 l and supplements the radiological effluent monitoring program by verifying that the measureable concentrations or radioactive materials and levels of radiation are not higher than expected on i the basis of the effluent measurements and the modeling of the l environmental exposure pathways. Guidance for this monitoring is i provided by the Radiological Assessment Branch Technical Position on  !

Environmental Monitoring (Revision 1, November 1979). Program changes may be initiated based on operational experience.

Requirements:

a. With the radiological environmental monitoring program not being conducted as specified in Table 1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the  ;

program as required and the plans for preventing a recurrence. l

b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium exceeding the reporting levels of Table 2 when averaged over any calendar quarter, prepare and submit to the commission within 60 days from the end of the affected calendar quarter, a special report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose

• to a member of the public is less than the calendar year limits. . When more than ene of the radionuclides in Table 2 are detected as the result of plant effluents in the sampling medium, this report shall be submitted if:

concentration (1) + concentration (2) + . . . > 1. 0 limit level (1) limit level (2)

• The methodology and parameters used to estimate the potential annual dose to a member of the public shall be indicated in this report.

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~ When radionuclides's other than those:inLTable 2:are detected an'd d

are the' result of.' plant effluents, this : report shall be . . .j submitted if the potentia 11 annual 'dese*:to a member of:the i

.public is equal to or greater than the calendar l year: limits; This report is not requiredLif the. measured level of radio- .

H activity was not the result'of plant, effluents;;however, in sucht 3 an event',1 the condition shall' be ' reported and. described,in ther Y Annual Radiological Environmental Operating Report.-

c. . With milk .o'r fresh leafy -vegetables unavailable 1from one 'or more

of the sample'1ocations. required by Table 1, identify locations-for obtaining replacement samples and add them to the' . .!

radiological environmental monitoring program within 30 days.

. The 1ocations from which samples were unavailable may thensbe '

" deleted.from the monitoring program. ,JIdentif,y the causelof the. 1 unavailability of samples.~and identify thinewilocation(s)ofor~.

obtaining replacement ". samples in..the next-' Semi- Annual . 1

, Radioactive. Effluent Release Rep' o rt:and also; include. in the; j report a revised figure (s) and table for the ODCM reflecting.the -

i new location (s). j 9  !

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• Th'e methodology and' parameters used to estimate.the' potential '

annual dose to a member of the public shall,be indicated in q' this report. '

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SHEET 4 of 4 ,

TABLE NOTATION

a. Sampling locations are provided in the ODCM. DeviationsareperEittid ,

from the required sampling schedule if specimens are unobtainable due to j

, , hazardous conditions, seasonal unavailability, malfunction of automatic -

sampling equipment and other legitimate reasons. All deviations from 4 l

the sampling schedule shall be explained in the Annual Radiological I Environmental Operating Report. l

b. Frequency notation: weekly (7 days i 25%), semi-monthly (15 days 25%),

monthly (31 days ; 25%), and quarterly,(92 days 25%).

c. One or more instruments, such as a pressurized ion chamber,. for measuring and-recording dose rate continuously may be used in place of, '

or in additi(n to, integrating dosimeters. For the purposes of thi-s i table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation.

d. Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more aftar sampling to allow for radon and thoron daughter decay. If gross beta' activity in air particulate samples is greater than 10 times the mean of control samples, gamma isotopic analysis shall be performed on the individual sample.

e. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility,

f. The " upstream sample" shall be taken at a distance beyond significant influence of the liquid discharge. The " downstream sample" shall be taken in an area beyond but near the mixing zone. ,

g. Composite sample aliquots shall be collected at time intervals that are short (e.g. hourly) relative to the compositing period (e.g. anthly) in order to assure obtaining a representative sample.

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I. CONDITION FOR OPERATION )

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2. Land Use Census ,

A land use census shall be conducted annually and shall identify within a distance of 8 km (5 miles) the location in each of the 16 ,

9 meteorological sectors, the nearest milk animal, the nearest garden

• q of greater than 50m2 (500 ft2) producing broad leaf vegetation, 1 and the nearest residence. This section is applicable at all {

times. Changes to this section must be approved by the NRC prior to implementation. '

These requirements are provided to ensure that changes in the use of l unrestricted areas are identified and that modifications to the l monitoring program are made if required by the results of this  ;

ce nsu s,. The best survey information from the door-to-door survey, '

aerial survey or consulting with local- agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet (50m2) provides assurance +

that significant exposure pathways via leafy vegetables wi'll be identified and monitored sinct a garden of this size is the minimum

' required to produce the quantity (26 kg/ year) of leafy vegetables )

assumed in Regulatory Guide 1.109 for consumption by a' child. To .

determine this minimum garden size, the following assumptions were '!

used, 1) that 20% of the garden was used for growing broad leaf vegetation (i.e. similar to lettuce and cabbage), and 2) a i vegetation yield of 2 kg/ square meter. l Requirements:

a. With land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the values currently being calculated, identify the new location (s), in the next Semi-annual Radioactive Effluent Release Report,

b. With a land use census identifying a location which yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with I.1 of this program, add the new location (s) to the radiological environmental monitoring program within 30 days. The sampling location, excluding the control station location, having the lowest

• Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different direction sectors with the-highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 1 shall be followed, including analysis of control samples.

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'l October 31' of 3 the year in which this'1and~use census was .i

• conducted, cIdentify the new location (s). in .the next Semi-annual .

Radioactive Effluent Release. Report and =.also include in'the' . , ' '

+1 report a revised figure (s)< and ; table for the 10DCM reflecting' the new location (r).-

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I. CONDITION FOR OPERATION a , j ,,

3. Interlaboratory ComparisoniProgram Analysis shall be performed on radioactive _ materials, supplied as ,

part of an' Interlaboratory' Comparison Program which has.been-approved by the NRC and is. required by Technical Specification 9- 6.8.1.i.. This'section is applicable at' all times. - '

The requirement for part.icipatibn _ int an'. approved Interlaboratory' Comparison Program :is provided to ensere that'. independent cht!cks.on- 4 the precision and accuracy L ~ of the measurements of radioactive =

i, material in environmental sample-matrices are performed asipart of a qJality assurance program' for environmental; monitoring in order to i -demonstrate that the results Lare. reasonably valid. ,

l' Requirements: 4 i

a. With ' analyses' not being performed as required above,; report the corrective actions taken to' prevent a recurrence to the .

Commission.in the Annual Radiological Environmental' Operating i Report.

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RADIOLOGICAL ENVIRONMENTAL MONITORD!G PROGRAM ~

II. MONITbRINGREQllIR'EMENTS 1

1. Sampling;and Analysis Methods . ,

The radiological environmental monitoring samples shall be collecte'd as described in Table 1 from the locations given in.the' table and ,.

figure (s) in the ODCM. These samples shall be analyzed as described in Table 1 usirig 'the detection . capabilities as described in Table.3.

2.- Land Use Census Methods 1

q The land use census'shall be conducted during the growing: season at s: 'least once annually, using- that information which will provide the. ~

best results such as 'doore to-door survey, aerial' survey, or by - q consulting' local agriculture' authorities. The results of the -land' i use census shall be included in the Annual Radiological Environmental Operating Report.  ; l

3. Interlaboratory Comparison Program A subary of the results obtained as part of the require'd Interlaboratory Comparison Program shall be included in the. Ahnual '

Radiological Environmental Operating Report..

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a This list does not mean that only these nuclides.are to be considered., ,  !

Other peaks"that are identifiable,iwhich may be related to plant i operations together with those of the above nuclides, shall 'also .be =l analyzed and reported in the Annual Radiological Environmental Operating- I

Report.

i b Required detection capabilities for thermoluminescent d'osimeters used for environoerital measurements are given in Regulatory. Guide 4.13. '

c, The LLD is deff ned, for purposes of these specifications, ~as the smallest -

concentration of radioactive material. in-a sample that will yield a. net' l

, count, above system background, that will be, detected with 95% .l probability with only 5% probability. of falsely concluding.that.a blank .'

i obs rvation represents a "real signal . ., i For a particular , measurement system, which may include radiochemical .

separation: >

l LLD = 4.66 sb .

, I E-r- V. 2.22 -

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' LLD is the "a priori" lower limit of detection as defined bove, as  !

picocuries per' unit mass or volume.

1 sb is the standard

• deviation of the background counting rate or of the l 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 disintegrations per minute pe'r picocurie.

Y is the fractional radiochemical yield, wt 'n applicable. ,

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.A is the radioactive decay constant for the particular adionuclide, and At for environmental samples is the elapsed time between sample- ..

collection, cr end of the sample' collection period, and time of coun'cing.

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

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, i It shocid 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. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally i background fluctuations, unavoidable small sample sizes, the presence of ,

interfering nuclides, or other uncontrollable circumstances may render '

these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Ahnual Radiological Environmental Operating Report, , ,

d LLD for drinking water samples.,

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