ML20004B982

Discusses TLD Direct Radiation Monitoring Network

ML20004B982
Person / Time
Site:	Summer
Issue date:	12/30/1980
From:	Stohr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Shealy H SOUTH CAROLINA, STATE OF
Shared Package
ML20004B928	List: ML20004B966 ML20004B980 ML20004B982 ML20004B989 ML20049A559 ML20049A562 ML20049A566
References
NUDOCS 8106010378
Download: ML20004B982 (24)

Text

[

UNITED STATES ATTACHMENT 3 yN NUCLEAR REGULATORY COMMISSION

^

~:-

E REGION 11 101 MARIETTA si., N W., SUITE 310o gs i

ATLANTA. CEonGIA 30303 j

otc 3,isso In Reply Refer To:

RII:JPS Mr. licyward Shealy, Chief Bureau of Raiological Health South Carolina Department of llealth and Environmental Control J. Marion Sims Building 2600 Bull Street Columbia, South Carolina 29201

Dear Mr. Shealy:

We greatly appreciate the cooperation shown by you ard your staff in assisting with the implementation of the TLD Direct Radiation Monitoring Network at the Summer Nuclear Station.

This program will provide independent measurements of radiation levels in the environs of this facility and will aid in assuring the validity of measurements made by the licensee. is a listing of TLD station locations by direction and distance from the Summer site including the NRC designation and siting criteria satisfied by the placement of each station.

In general the siting criteria provide for an inner ring (I) and an outer ring (0) of TLD stations at one to two miles and three to five miles from the site, respectively.

One inner ring and one outer ring station should be in each of the 16 sectors where practical.

Provision is also made for locations of high public interest (HP1), population centers of 25,000 or more (P), populated areas of less than 25,000 (PA), sites co-located with the licensee (C) and the nearest resident (NR).

Upwind controls are ordinarily situated approximately 15 to 20 miles f rom each site in the least frequent wind direction.

I consists of a proposed route for exchanging the TLDs at the Summer site.

These detailed descriptions and diagrams are meant to allow persons unfamiliar with the site to locate the TLDs in a step by step manner. The State is by no means constrained to exchange "the TLDs in the order indicated in this enc 1csure.

l l

The annealed envirorur. ental TLDs will be sent by NRC Region I to your office for exchange on a quarterly basis, that is, within seven days prior or seven days after the beginning of each calendar quarter.

An "in transit control" TLD l

package will be included with the other exchange TLDs for placement at the state of fices in as low background an area as you have available.

Experience shows that a certain number of TLD stations will be vandalized or otherwise lost.

Should this be discovered during the quarterly exchange we request that the state replace the missing TLD cages with NRC provided spares and inform this office.

This is especially important if it was necessary or

[

expedient to move the station enough to make the exchange route write-up invalid.

l If for any reason discrepancies in the exchange route write-up (Enclosure 2) come to your attention, we request that. we b informed.

l THIS DOCUMENT CONTAINS l

8106010373 POOR QUAUTY PAGES.4

DEC a 01980 jfeyvard Shealy,

The data generated by this program concerning the Summer. Nuclear station will be made available to your office in the form ot annual and quarterly reports which should commence in 1981.

It is planned that the reports be sent out within a month af ter the end of the reporting period.

Please do not hesitate to call D. M. Montgomery (404/221-5572) of my staff should you have questions regarding this program.

Sincerely,

. ilip S ' hr, Chief Fuel Facility and Materials Safety Branch

Enclosures:

1.

Surner TLD Stations 2.

Summer TLD Exchange Route cc w/encls 1&2:

Su:;an k'elch, South Carolina Department of llealth and Environmental Control

,t.

ENCLOSURE 1 ENVIRONMENTAL RADIATION MONITORING STATIONS NRC TLD NETWORK VIRGIL C. SUMMER NUCLEAR STATION NRC

• CRITERIA STATION LOCATION DESCRIPTION SATISFIED 11 N, 3490, 4.3 milta Rt. 11, 0.7 mile East of Rt. 257 0, C**

10 N, 7, 4.0 miles Rt. 11, 0.7 mile West of Rt. 215 0

N No Inner Ring Station, not accessible 9

NNE, 130, 3.9 miles Intersection Rt. 215 and Rt. 11 in Monticello 0, C**

8 NNE, 310, 3.0 miles Rt. 213/215, 0.5 mile North of Rt. 359 0

NNE No Inner Ring Station, Not accessible 7

NE, 46,' 3.0 miles Rt. S 20 359, 0.4 mile East of Rt. 213/215 0

6 NE, 540, 1.5 miles Rt. 224, 0.5~ mile West of Rt. 213/215 I

16 ENE, 640, 3.5 miles Old Brick Church on Rt. 213 0

5 ENE, 720, 1.8 miles White Hall School on Rt. 213/215 I, RPI 4

E, 860, 0.5 mile Rt. 213/215, 0.5 mile North of Site Road I

17 E, 980, 3.1 miles Rt. 247, 1.6 miles Southeast of Rt. 213 0

2 ESE, 1110, 1.0 mile Rt. 311 (Site Road), 0.3 mile West of Rt. 215 I, NF.

18 ESE, 114, 3.5 miles Stella Hill residence on Rt. 247 0

19 SE, 1320, 2.0 miles Rt. 213/215, 0.2 mile North of Rt. 247 I, C**

21 SE, 1330, 4.1 miles Rock Hill Church on Rt. 215 0, HPI t

40 SE, 135, 23.1 miles Intersection of Rt. 321 and Buckner St. in Columbia P

39 SE, 140, 25.0 miles S.C. Department of Health and Environmental Control P

38 SSE, 1480, 20.8 miles Majik Market near intersection of St. Andrews Road and Rt. 76 in Columbia P

20 SSE, 152, 4.5 miles Lookout Tower Rd., 1.7 mile South of Rt. 215 0

22 SSE, 1570, 2.4 miles Rt. 213, 0.7 mile West of Rt. 215 I, C**

23 S, 1730, 2.4 miles Rt. 216 (to Parr), 0.3 mile West of Rt. 213 I

37 S, 182, 14.8 miles Intersection of Rt. 270 and Rt. 1254 (Libby Arial Cir)

UWC 0

36 S, 183, 14.6 miles Rt. 270, 0.5 mile South of Putnam Road UWC i

35 S, 1840, 14.1 miles Intersection of Rt. 270 and Putnam Road near Lake Murrey Park UWC 24 S, 185, 3.9 miles Mount Herman Church in Peak, South Carolina 0, PA, C**

HPI l

l e

34 SSW, 1920, 9.3 miles Intersection of Rt. 76 and Clark St. in Chapir, SC PA 1

SSW, 1990, 3.7 miles Wicker's Store, Rt. 28 and Rt. 213 0, C**

25 SSW, 210, 3.3 miles Rt. 28, 0.8 mile North of Rt. 213 0

SSW No inner ring station, not accessible 26 SW, 2170, 3.3 miles Rt. 28, 1.2 miles North of Rt. 213 0

33 SW, 218, 9.0 miles Intersection of Rt. 202 and Rt. 76 in Little Mountain, SC PA 27 SW, 231, 3.1 miles Rt. 28, 2.1 miles north of Rt. 213 SW No inner ring station, not accessible 31 WSW, 244, 3.6 miles Rt. 33, 0.8 mile west of Rt. 28 0

32 WSW, 247, 6.2 miles Pomaria Fire Department on Rt. 107 PA 14 WSW, 255, 2.8 miles Rt. 28 at Cannons Creek 0

WSW No inner ring station, not accessible 28 W, 267, 2.7 miles Rt. 28, 1.6 miles north of Rt. 33 I

29 W, 276, 3.4 miles Rt. 98, 0.5 mile west of Rt. 28 0,

C**

30 WNW, 293, 3.8 miles Rt. 28 at Parr reservoir accese area 0

WNW No inner ring station, not accessible 15 NW, 308, 5.6 miles Intersection Rt. 28 and Rt. 97 0

12 NW, 323, 5.0 miles Rt. 651, 2.2 miles west of Rt. 257 0

NW No inner ring station, not accessible 13 NNW, 333, 3.0 miles Rt. 257, 2.3 miles south of Rt. 383 0

3 NNW, 340, 4.1 miles Intersection of Rt. 257 and Rt. 383 0,

C*

• NNW No inner ring station, not accessible t

I QCriteria:

I - Inner Ring; O - Outer Ring; P - Population Center; HPI - High Public Interest; UWC - Upwind Control; C - Co-located with licensee; NR - Nearest Residence; PA - Populated Area (less than 25,000) ocCandidate Stations for co-location with the licensee.

SCE&G will co-locate with five out of the eight devices indicated when they i=plement their expanded IID Program.

l ATTACHMENT 4 0

O n

n-j c

c 0

e e

/

New TLD "TL Badge System" l

l TL Badge: Model UD 800 Series Automatic Reader: Mode! UD-710 Series Magazine changer: Model UD-730 Series j

fj f

1 E

l 8

i l

9'

's.

l = ~ " " ~ ' \\D 'N !d j Ws,% Q TL Badge with Hanger; UD-600 Senes g l i l \\%, l Magazine Changer: Model UD 730 s TLD Automatic Reader: Model UD.710 l This system can be used for periodival personnel monitoring of As the detectors of the TL badge, tissue-equivalent material (Li Ba0 :Cu)* and I.ighly sensitive material (CaSOa :Tm) are people who work in a field of radiation. 2 3 This is suitable for use not only in large facilities, such as a used, making it possible to precisely measure various kinds of nuclear power plant, but in middle or small size facilities such radiation in a wide range. as a hospital or a laboratory. By utilizing the optical-heating method *, the reader is designed to measure the TL badges quite easily and quickly.

• Patent pending l

.r J $$h s~ = s ~ ,y yyymn]TllllHmmIw.i'mMM. L l Magazine. Model UD 740 N r*, e i ei TLD Automatic fleader: Model UD 710 By the optscal heating method, the reader can measure many TL Specifications badges at high spec " ith stability. One thin TLD element TLD Automatic Reader: Model UD-710 Series can be heated in by tne flashing light of a tungsten l With magazines limp. Both the .e counting method and the current Badge-feed system I integraiion method are en. ployed to precisely detect the ther-(50 badges / magazine) moluminescence throughout a wide range from low doses to Reader.g method l high doses. Peating Optical heating method l The reader is equipped with a microcomputer which controls TL Measurement 1 Pulse counting method (for small signals) self<hecking functions and all automatic functions, such as current method ennealing of the TL badges for repeat use, reading of the ID code, and sensitivity adjustment for correction by the built- _ _. O r large signats) _~ l m rzference light source. The processing time is greatly shor tened. Pre-heating and Annealing i Pre heating and annealing so that total time for one badge (4 elements) is only 20 seconds. ! functions are incorporated. I ! Optical reading Furthermore, by using a magazine changer (optional), 500 ID code reading ~ badges can be measured in 3 hours without manual operation. Processing speed 20 seconds / badge 3 hours /500 badges The measured data is displayed on the display ponel of the reader. (utilizing magazine changer) and the reader is alsoequippedwith an interface for transmitting ~ Chec. king of optical path, the data to outside equjpment such as a computer or a printer, self. checking functior15 sensitivity of PM tube, heating stabil.ty, etc. Output interf ace-RS-232C j F:atureS Dimensions and Weight i 543(W) x 830(H) x 380(D)mm j 77kg o TL Badges can be fed into the leader without the necessity Magazine Changer: Model UD 730 Series for manual operations such as opening the case and taking out the elements. Capacity I 10 magazines (500 oadges) o Large processing capability and high speed measurement. Dimensions and Weight , 485(W) x 790(H) x 346(D)mm o Equipped with self<hecking functions. G1kg

m b a ' .' \\ 4L E 'N \\ ,1 Nr /O/ .N th);, ?e OL O O Oi UD-SO2A... ' oc . ~ .%5137.E.Of h_ TL Badge: Model UD-602A This is a small, very reliable dosimeter which is designed not SPOCificationS only for superior characteristics as a dosimeter but also te include all desirable points, such as easy handling, cleanliness. TL Badge: Model UD.800 Series resistrnce to mcchanical impact, etc. Type ! Composite type of 2 to in the detection part,a newly developed ;,.aosphor (Li 8 O,:Cu) 2 4 and a highly sensitive phosphor (CaSO :Tm), both formed to a - ! 4 elements. 4 then element, are used. They are also especially designed for g opticil heating. Elements: Phosphors Li 8 03:Cu 2 4 Li 0 0 :Cu has a radiation respons-characteristic which is CaSO :Tm 4 7 4 very close to that of human tissue, and responds precisely to X (diameter 3mm x 15 n g/cm ) 2 l Skin dose rays and y rays in a wide range from low energy to high energy. Measurable rays X rays, y rays; 10 kev ~ 10MeV Furthermore, because the element is very thin, the skin dose can be measured. Measurement range ! ImR ~ 1000R On the other hand, CaSO :Tm has very high sensitivity, and a Fading 4 very small dc se can be detected with this phosphor. Furthermore, (at room temperature) Li 8403:Cu < 10%/ month 2 low-energy X rays and y rays can be detected separately by ' CaSO :Tm < 1%/ month 4 utilizing the energy characteristics of the phosphor. Spurious signal Undetectably small Elements are encased in a holder. The ID number is coded by Dimensions and Weight l 49 x 23 x 6mm 79 punched holes, and they are read automaticall r by the reader. (with hanger) (13 ) i 9 A hanger with clip is used for wearing. Features Energy dependence is small and ser sitivity is high. Skin doses can be measured.

• Small and lightweight.

ID codes of large capacity can be punched.

• The lock mechanism prevents accidentel contamination of detection part.

Reading method and construction Element plate 7 Slide / Dosimeter holder t Reference fight source 4 / Dosimeter element 0 /- ~ _ tamp Silicon filter y } ./ ' / h, )Y'y * / N Photomultiplier ) \\,- e s. 'NN w

• h'i p' '

/ NN\\ ,/' ID Code reading unit N.- / i / s Magazine Construction of the model UD-802A, a typical TL badge, and the energy responses of each element. 2 1st element j Li B40 :Cu 2 3 g, / behind thin indo.s Q fe,, 2 2nd element E o Li BaO,:Cu Eg' 1, 0 j eehind grastic. airs 1 l7 ', ##2?ik j0' i i i 4(0 E a _.'k ' ):: _- 3rd element E \\ CaSO :Tm 2 10 l 4 - 0 nehind piast;c.aiis i e T $ 6--- e 1 \\ l \\ 0> i i l O 2 Ca5 4 T A / 3 / TL Badge: Model UD-802 A' behind lead shields O i i i i 0.01 0.1 1 10

• There are several models in the UD - 800 series.

Photon energy (MeV) Please request details concerning other mode's. Speed. cations are sutoect to change..tnout notice for f u.imer.n.orowment Panasonic Panasonic Company Division of Matsushita Electric Corporation of America One Panasonic Way. Secaucus. New Jersey 07094 let No 201348 72e. 20i 34.4 7.,1. Ch.caac Of f.ce 1d No 312 455 3:05 PDD 78 003 Premted en Japan.

AiltCh"E*.T 5 Revision 1 November 1979 Branch Technical Position jacieround Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants, issued for comment in December 1975, is being revised based on comments received. The Radiological Assessment Branch issued a Branch Position on the radiological portion of the environmental monitoring program in Marca, 1978. The position was formulated by an NRC working group which considered comments received after the issuance of the Regulatory Guide 4.8. This is Revision 1 of that Branch Position paper. The changes are marked by a vertical line in the right margin. The most significant change is the increase in direct radiation measurement stations. 10 CFR Parts 20 and 50 require that radiological environmental monitoring programs be estaolished to provide data on measurable levels of radiation and racioactive.aterials in the site environs. In adcition, Appendix I to 10 CFR Part 50 requires that the relationship between quantities of radioactive caterial released in effluents during normal operation, including anticipated coerational occurrences, and resultant radiation deses to indiviouais from principals pathways of exposure be evaluated. These programs should be con-ducted to verify the effectiveness of in plant measures used for controlling the release of radioactive materials. Surveillance should be estaclished to icentify enanges in the use of unrestricted areas (e.g., for agricultrual purposes) to provide a basis for modifications in the monitoring programs for evaluating doses to individuals from principal pathways of exposure. NRC Regulatory Guide 4.1, Rev.1, " Programs for Monituring Radioactivity in 7"e Environs of Nuclear ?ower Plants," provides an acceptable basis for the i; sign of programs to monitor levels of radiation and radioactivity in the station environs. This position sets forth an example of an acceptable minimum radiological monitoring p ogram. Local site characteristics must be examined to determine if pathways not covered by ;his guide may significantly contribute to an indivicual's dose and should be included in the sampling program.

2 AN ACCEPTABLE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ?;3_ oram Recuirements Environmental samples shall be collected and analy:ed according to Table 1 at locations shown in Figure 1.1 Analytical techniques used shall be such that the detection capabilities in Table 2 are achieved. The results of the radiological environmental monito,ing are intended to supplement the results of the radiological effluent monitoring by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measure-ments and modeling of the environmental exposure pathways. Thus, the specified environmental monitoring program provides measure.ments of radiation and of radio-active materials in those exposure pathways and for those radionuclides whicn lead to the highest pntential radiation exposures of individuals resulting from the station oceration. The initial radiological environmental monitoring program snould be concucted for the first three years of commercial operation (or other ceriod corresponding to a maximum burnup in the initial core cycle). Following nis period, program changes may be proposed basea on operational excerience. The specified detection cacabilities are state-of-the-art for routine environ-mental measurements in industrial laboratories. Deviations ara per.aitted from the required samoling schedule if specimens are uncetainacle due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunc.fon, every effort shall be mace to comolete corrective action prior to the end of the next sampling l l oeriod. All deviations from the sampling schedule shall be documented in the annual report, l .he laboratories of the licensee and licensee's contractors whicn perform l analyses snall participate in the Environmental Protection Agency's (E?A's) l Environmental Radioactivity Laboratory Intercomparisons Studies (Crosscheck) Program or ecuivalent program. This participation shall include all of the

eterminations (samole mediuni radionuclide combination) that are offered by l

!?A anc that also are included in the monitoring arogram. The results of l 2nalysis of these crosscneck sacples snall be included in the annual recort. The participants in the EPA crosscheck program may provide their E?A program

oce so that the NRC can review the E?A's participant data directly in lieu of seemission in :ne annual recort.

I ^

may be necassary to require special studies on a case-by-case and site soecific basis to estan11sh the~relationsnip between quantities af racicactive material released in effluents, the concentrations in environmental mecia, and tne resultant doses for important pathways.

l l

3 If the results of a determination in the EPA crosscheck program (or equivalent program) are outside the specified control limits, the laboratory shall invas-tigate the cause of the problem and take steps to correct it. The results of this investigation and corrective action shall be included in the annual report. The requirement for the participation in the EPA crosscheck program, or similar program, is based on the need for independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonaoly valid. A census shall be conducted annually during the growing season to determine the location of the nearest milk animal and nearest garden greater than 50 square meters (500 sq. ft.) producing broad leaf vegetation in each of the 16 meteorological sectors within a distance of a km (5 miles).2 For elevated releases as defined in Regulatory Guide 1.111, Rev. 1., the census shall also icentify the locations of all milk animals, and garcens greater than 50 square metars producing broad leaf vegetation out to a distance of 5 kn. (3 miles) for each radial sector. If it is learned from this census that the milk animals or gardens are present at a location which yields a calculated thyroid dose greater than those previously samoled, or if the census results in changes in the location used in the racioar,tive effluent technical specifications for dose calculations, a written l recort shall be submitted to the Director of Operating Reactors, NRR (with a l copy to the Director of the NRC Regional Office) within 30 days identifying the new location (distance and direction). Milk animal or garden locations .esulting in highar calculated doses snall be added to the surveillance program Ts < con as practicable. l l The sampling location (excluding the control sample location) having the l lowest calculated cose may then be drcpped from the surveillance program at l the end of the gra:ing or growing season during wnica the census was con-l cucted. Any location from which milk can no longer be obtained may be dropped from the surveillance program after notifying the NRC in writing that they are l no longer catainable at that location. The results of the 'and-use cansus snail be reported in the annual recort. The census of milk animals and gardens producing broad leaf vegetation is cased on the requirement in Appendix I of 10 CFR Part 50 to "!centify cnanges in the use of unrestricted areas (e.g., for agricultural purposes) to permit mooifications in monitoring programs for evaluating cases to indivicuals from principal pathways of exposure." The consumption of milk from animals grazing i l an contaminated pasture and of leafy vegetation contaminated by airborne l 3 road leaf vegetation sampling may be performed at the site bouncary in a sector with the highest D/Q in lieu of the garden census. l l

4 radiciodine is a major potential source of exposure. Samples from milk ani als are considered a better indicator of radiofodine in the environment t* a vegetation. If the census reveals milk animals are not present or are unavailable for sampling, then vegetation cust be sampled. The 50 square meter garden, considering 20% used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and a vegetation yield of 2 kg/m, t 2 l will produce the 25 kg/yr assumed in Regulatory Guide 1.109, Rev 1., for cafld consumption of leafy vegetation. The option to consider the garden to be broad leaf vegetation at the site boundary in a sector with the highest D/Q should be conservative and that location may be used to calculate doses cua to radioactive effluent releases in place of the actual locations which would ba determined by the census. This option does not apply to plants with elevated releases as defined in Regulatory Guide 1.111, Rev. 1. The increase in the number of direct radiation stations is to better characteri:e the individual exposure (mrem) and population exposure (man-rem) in accordance with Criterion 64 - Monitoring radioactivity releases, of 10 CFR Part 50, Aopenoix A. The NRC will place a similar amount of stations in the area cetween the two rings designated in Table 1. Resorting Recuirement A. Annual Environmental Operating Report, Part 8, Radiological. A report on the radiological environmental surveillance program for the i previous calendar year shall be submitted to the Director of the NRC Regional Office (with a copy to the Director, Office of Nuclear Reactor i Regulation) as a secarate document by May 1 of each year. The period of the first report shall cegin with the date of initial criticality. The ( reports shall include a suanary (format of Table 3), interpretations, and an analysis of trends for the results of the radiological environmental surveillance activitie; for tt.e report period, including a comparison with operational controls, ; eoperational stucies (as appropriate), and previous environmental surveillance reports anc an assessment of the coserved impacts of the station operation on the environment. In the event that some results are not availaole the report shall be l ) suomittud noting and exclaining the reasons for tne missing results. The missing cata shall be submitted as soon as possible in a supplementary repo rt. The reports shall also include the following: a summary descriotion of tne radiological environmental monitoring program; a maa of all :a.:.pling locations keyed to a table giving distances and directions from one reactor; the results of land use censuses; and the results of licensee carticipation in a lacoratory crosseneck program if not participating in One EPA crosscheck program.

5 8. Nonroutine Radiological Environmental Operating Reports "If a confirmed 3 measured radionuclide concentration in an environmental sampling medium averaged over any quarter sampling period exceeds the reporting level given in Table 4, a written report shall be submitted to the Director of the NRC Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulation) within 30 days from the end of the quarter. If it can be demonstrated that the level is not a result of plant effluents (i.e., by comparison with control station or preopera-tional data) a report need not be submitted, but an explanation shall be given in the annual report. When more than one of the radionuclides in Taole 4 are detected in the medium, the reporting level shall have been exceeded if: concentration (1) concentration (2) . ~~~> 3 reporting level (1) reporting level (2) If radionuclides other than those in Table 4 are detected and are due from plant effluents, a reporting level is exceeded if the potential annual dose to an individual is equal to or greater than the design objective doses of 10 CFR part 50, Appendix I. This report shall include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous result. 'A confirmatory reanalysis of the original, a duplicate, or i new sample may oe desiracle, as appropriate. The results cf the confirmatory analysis shall be cocoleted at the earliest time consistent with the analysis, but in any case within 30 days. l i l

MI E I OPLIIA110llAL l{Aul010GICAL El4Vihutilitill AL H0111IUl(It4G l'l(OGilAll Lepo,nse Pathway lion.her of samples" sair.lil isig asid Type and frequency and/or Sau.ple acid Locatiosis Collection frequency # and Analysis AlltitulGIE Itadioindsne and Saiuples f roin 5 locations. Continuous san.pler itadioiodine Cannister: Particulates operatioin with saniple analyze weekly for 3 samples from offsite locations collection weekly or I-131 (in different sectors) of the as requ! red by dust highest calculated annual average loadista. wlilegever is groundlevel D/Q. siore frequent I sample from the vicinity of a Particulate Sampler: comnionity having the highest Gross beta radio-calculated atinual average grousid-activity folleging level D/Q. filter change, composite (by locagion) for gamma isotopic quarterly m I sample from a contros location ] 15-30 kna (10-20 miles) distant asid d in the least prevaluint wisid direcL!on

lill(LCi 1(Alll A110ll 40 stations with two or more dosi-Monthly or quarterly Ganuna dose monthly or (

meters or olie instrument for measurisig quarterly aiul recording dose rate contiatinously to be placed as follows:

1) asi isisies-ring of statio:is isi llic genieral area of the site bs.andary aind dit ointer risig in the 4 to 5 mile rasige frosu the site wit.

a stationi in eacli sector of each risig (16 sectors x 2 rings = 32 stations). the balasice of Llie stations, 8, should be place ist special interest areas nucle as llopulatioli ceiiters, siearby residences, schools, and in 2 or 3 areas to serve as control statioins. 1

TADt E I (C::ntinued) Iaposiere Pathway thmiber ut Saiaples" Sampiisig asid type and frequency and/or Sample asid locatiosis Collection frequency" of Analysis a t/A Ii 1:11010lt d Surface I saliiple upstreain Composite sainiple Gainizia isotopic analysis ' bample downstream one month period *yer h monthly. Composite for tritium asialyses quarterly Ground Samplesfrom1or2sourgesonly Quarterly Gangua isotopic and il likely to be affected trititua analysis quarterly Orinkihu I sample of each of 1 to 3 of Composite sample I-131 analysis on each g the nearest water supplies over two-week period composite when the dose could be affected by its if I-131 anlysis is calculated for the con-discharge performed, monthly sumption of the water composite otherwise is greate 1 sample from a control location per year.p than 1 nreni Composite for Gross 11 and gamma isotopic y analyses monthly. Compo-site for tritium analysis quarterly Sedimeint f roni I souiple frosa dowsistream area Semiantiually Ganuna isotopic analyses Shcreline with existing or potential semiannually recreational value litGI $ f 1014 Hilk Samples from milking animals Semimonthly when ani-Gamma isotopic and I-131 in 3 locations within S kan mals are osi pasture, analysis semimonthly when distant havisig the liigliest dose monthly at other times animals are on pasture; potential. If there are none, monthly at other tilines.

then, I sample from milking animals in each of 3 areas between 5 to 8 km distant where doses are calcislated to he k

greater than I mrem per year

TAllt E I (Continued) In one Patt.way linn.ber of samples," Sampiisig asid Type and frequency oml/or Son.p le asid Locations Collection Ircquency' of Analysis Hilk (cont'd) I saisiple f rom milking anisaals at a cositrol location (15-30 km distant asid in the least prevalenit wind diret. tion) fish and I sample of each comaiercially and Sample in season, or Ganvaa isotopic Invertebrates recreatiosially important species semianually if they are analysis on edible in vicinity of discharue point not seasonal portions I sample of same species in areas not influenced by plant discharge I Food Products I sample of each principal class At time of harvest Gamma isotopic of food products from any area analysis on edible which is irrigated by water in portion. which liquid plant wastes have been dischar0ed on 3 samples of broad leaf vegetation Monthly when available grown nearest offsite locations of hl0 hest calculated annual average grousul-level D/Q if allk j sampling is not performed I sample of each of the similar Honthly when avalleSle vegetation grown 15-30 km distant in the least prevalent wind direction if anilk sampling is not performed

TABLE 1 (Continued) 6 t he nim.ber, media, f ressisesicy and location of sampling may vary f rom site to site. It is recognized that, at Linies, it may nuL be possible or practical to obtaisi sempies of the media of clioice at the most desired location or time. instances suitable altertiative suedia and locations may be chosen for the particular pathway in question l In Liiese j dsid submilled Ior aCCeplailce. Actual locations (distance asid direction) from the site shall be provided. Refer to Hegulatory Guide 4.1, "Prograins for Honitoring Radioactivity in the Environs of Nuclear Power Plants." I' Particulate mple filters should be asialyzed for gross beta 24 liours or more af ter samplitig to allow for radon and 1 thoron daughter decay. If gross beta activity las air or water is greater than ten tienes the yearly mean of control samples for any medluna, galiima isotopic asialysis should be performed on the individual san 1ples. ) Gamma isotopic analysis mediis the identificationi and quantification of ganiina cailtting radionuclides that may be C i oLLribi Lable Lu the ef flisesils fr osa the facility. "The piirpose of this sample it. La obtain background inforniallon. If it is not practical to establish control loca-tions in accordance with the distance and wind direction criteria, other sites which provide valid background data aay be substituted. " Canisters for the collection of radiolodine in air are subject to channeling. These devices should be carefully c.iecked before operationi lei the field on several should be mousited in series to prevent loss of iodine. 4 I Hegulatory Guide 4.13 provides minimula acceptable perforniance criteria for thermoluminescence dosimetry (TLD) t syst ems used for environmental monitoriang. One or niore instruments, such as a pressurized ion chamber, for measur-ing oud s ecording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a Lliermoluminescent dosimeter may be considered to be one phosphor and two or more + phosp;iors lsi a packet siay be considered as two or more dosimeters. Film badges should not be used for measuring direct radiation. The 40 stations is rioL an absolute nuaiber, lhis ciuisiber may be reduced according to geographical limitatiosis, e.g., at asi oceali site, sonne sectors will be over water so that the number of dosimeters may be reduced accordisigly. U lhe "upstrean sample" should be taken at a distance beyond significant influence of the discharge. The "down-strea.a" sample should be Laken in an area beyond but near the mixing zone. " Upstream" saniples in an estuary asust be token f ar etioisgh upstreasa Lo beyond the plant influence. h Generally, salt water is not sampled except when the receivisig water is utilized for secreational activities. I Composite sas.ples should be collected with equipment (or crpilvalent) which is capable of collecting an aliquot at Lisiie initesvals whicli are very short (e.g., hourly) relative to the compositing period (e.g., monthly). 3Groundwater saaples should be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradiesil or reclidrge properties are suitable for contaanination. 'k nu dose shall be calculated for the maximtua organ aiul age group, using the methodology contained in Regulatory Guide 1.109, Hev.

l., aind the actical pas ameters particular to the site.

I ll harvest occurs more than once a year, sampling should be performed during each discrete harvest. If harvest ou. ors conLini.ously, sampling should be monthly. ALLention should be paid to including saniples of Luborous and soul fuod products.

IAl}lE 1 (Continued) flu t e: Isa addition to the alsove giaidasice los operat iosial moniitorisig, tiie f ollowisig siaterial is sispplied for guidance 04: preoperatiosial gis ogi aisis. Preoperatiosial Esivirosiniesital Surveillasice Program A Preopes atiosial Envirosinierital Surveillarice Prograiu sticuld be instituted two years prior to Llie institution of station plant opei dtiosi. the purposes of this prograin are: 1. To saeasure background levels and their variations alusig the ainticipated critical palliways in the crea surrounding the station. 2. To train personnel 3. Io evaluate procedures, equipment and techniques Ihe elements (sampling media and type of analysis) of both preoperational and operational programs should be essen-t ially Llie sariie. The disrationi of the preoperational program, for specific siedia, presented in the following table should be follot4ed: Ihirationi of Preoperational Sanipling Frograin for Specific Media g 6 moniths 1 year 2 years . airliorsie lodifie . dirborne partiCGldles . direCL radiation iodine in milk (while . milk (reniaisiing analyses) . fish and invertebrates d84 Ilials are ili liaslure) . surface Waler . food products . groundwater . sediment from shoreline . drinking water

IABLE 2 lietection Capabill!.ies for Esivironisinesital Sample Atialysis' Lower Limit of Detection (LLD)b Airborne Particulate Water or Gas Fish flilk food Products Sediment Anaysis (pCi/l) (pCi/m3) (pCi/kg, wet) (pci/l) (pCi/kg, wet) (pCl/kg, dry) Dross beta 4 1 x 10~ ll 2000 lin 15 130 59Fe 30 260 58,60 2 C0 15 130 6S in 30 260 lr 30 U' ill: 15 I3I c -2 l i ./ x 10 1 60 134 -2 Cs 15 5 x 10 130 15 60 150 I3# -2 Cs 18 6 x 10 150 18 80 180 ISUlla 60 60 1401a 15 15

llute

liais list does not inicani liiat only these nuclides are to be detected asid reported. Other peaks which are measuratale asial lileistifialite, touellier willi Llie above nuclides, stiali also be identified and reported. 4

I 12 TABLE 2 NOTES aAcceptable detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13. DTacle 2 indicates acceptable detection capabilities for radioactive materials in environmental samples. These detection capabilities are tabulated in terms of the lower limits of detection (Llos). The LLD is defined, for purposes of this guide, as the smallest concent ation of radioactive material in a sacole that will yield a net count (above system background) that will be detected with 9E% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measuremant system (which may include radiochemical separation): 4.66 s b LLD = E V 2.22 Y-exp(-Aat) where LLD is tne "a priori" lower limit of detection as defined above (as pCi per unit mass or volume). (Current litarature defines the LLO as the detection capability for the instrumentation only, and the MDC, minimum detectable concentration, as the detection capability for a given instrument, procedure, and type of sample.) b is the standard deviation of the background counting rate or of s the counting rate of a blank sample as apprcoriate (as counts per minute) E is the counting afficiency (as counts per disintegration) V is the sample size (in units of mass or volume) 2.22 ia the numcer of disintagrations per minute per picocurie Y is the fractional radiochemical yield (when applicable) A is the radioactive decay constant for the particular radionuclide at is the elasped time between sacole collection (or end of the sacole collection period) and time of counting The value of 5 used in the c? culation of the LLD for a particular measure; t 3 ment system snauld be cased on the actual observed variance of the ack-grouno counting rate or of the counting rate of the blank samoles (as accroariate) rather : Man on an unverified theoretically predicated variance.

13 In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background should include the typical contributions of other radionuclices normally present in the samples (e.g., potassium-40 in milk samples). 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 criori (before the fact) limit representing the capability of a measure'ent system and m not as a costeriori (efter the fact) limit for a particular measurement." CLLD for drinking water samples. C For a more comolete ciscussion of the LLD, and other detection limits, see the following: (1) HASL Procedures Manual, HASL-300 (revised annually). (2) Carrie, . A., " Limits for Quaittative Detection ano Ouantitative Determination - Application to Radiocnemistry" Anal. Chem. 30, 586-93 (1968). (3) Hartwell, J. K., " Detection Limits for Radioisotopic Counting Technicues," Atlantic Richfield Hanford Ccm:any Report ARM-2537 (June 22, 1972).

IAlllE 3 tiiVihollittill AL l(All1010GICAL Holill0HillG l'HOGl(All AlitiUAL SUHilARY liame of Fociiity Ilocite L llo. __ _ locationi ul iatility _ _ _ 1(epos Liaisj Per-iod (County, State) !!.:d eimi or Type and lower Limit All Indicator Location witti liighest Controllocatfons Number of - potlaway Sampled loLal fiumber of localicsi Asisitaal Heati Heasi (f) Nonroutine Hean (f)g Mame Mean (f)b Rantje Reported (llnit of of Analyses Detectioni Heasurement) Performed (LLD) Range Distance & Range Measurements Direction Air Particii-lati:s (pCi/m ) Gross (1 416 0.01 0.08(200/312) Hiddletown 0.10 (5/52) 0.00 (0/104) 1 (0.05-2.0) 5 miles 340* (0.08-2.0) (0.05-1.40)

• y-Spec. 32 137
• 0.01 0.05 (4/24)

Smithville 0.08 (2/4) <LLO 4 C (0.03-0.13) 2.5 milles 160* (0.03-2.0) 131 0.07 0.12 (2/24) Podunk 0.20 (2/4) 0.02 (2/4) 1 5 g (0.09-0.18) 4.0 miles 270* (0.10-0.31) lish pCi/lqj (wet wei ht) y-Spec. 8 U 137 130 <tLD <LLO 90 (1/4) 0 Cs 134 130 MD 60 GD 0 Cs 60 130 180 (3/4) River Hile 35 See Column 4 <LLD 0 (150-225) "See l ati l t-2, siale 13 iteau an.d rance based upon tietecluble i;*castiressiesits only. Fraction of detectable measurements at specified locations is isuiicated sin lias esitheses. (f) llate: the example data aio provided for illustrative lusrposes only.

tar E 4 HEPORIING LEVELS FOR NONROUllNE OPERAIING REPORTS Reporting Level (llL) Broad Leaf Water Airborne Particulate Fisli Milk Vegetation Asialysis (pCi/l) or Gases (pCl/m ) (pCi/Kg,wel) (pCi/1) (pCi/Kg, wel) 3 4Id3 li-3 2 x 10 3 4 Mn-54 1 x 10 3 x 10 2 4 Fe-b9 4 x 10 1 x 10 3 4 Co-58 1 x 10 3 x 10 2 4 Co-60 3 x 10 1 x 10 4 In-65 3 x 10 2 x 10 Ir-ilb-95 4 x 10 0 2 1-131 2 0.9 3 1 x 10 3 Cs-134 30 10 1 x 10 60 1 x 10 3 Cs-13/ 50 20 2 x 10 70 2 x 10 2 2 um-La-140 2 x 10 3 x 10 "for drinking water samples. Iliis is 40 Cfit Part 141 value.

i l ~16 I 1 1 I Figure l' (This figure shall be of a suitable scale to show the distance and direction of eacn monitoring station. A key shall be provided to indicate what is sa:: pled at each location.) I l t s i I. i i I I r I l l l [ .,e, -,,--v_ n ,.. _ - - - - -. ~,,,, - - - -... -}}