ML19345F367

Testimony in Response to Contentions EP-3(C)(1) & EP-18 & ASLB Question 4 Re Offsite Radiological Monitoring

ML19345F367
Person / Time
Site:	Three Mile Island
Issue date:	02/09/1981
From:	Riethle W GENERAL PUBLIC UTILITIES CORP.
To:
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ML19345F365	List: ML19345F364 ML19345F367 ML19345F384 ML19345F387
References
NUDOCS 8102170350
Download: ML19345F367 (23)

Text

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Lie 2/9/81 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )

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METROPOLITAN EDISON COMPANY ) Docket No. 50-209

) (Restart)

(Three Mile Island Nuclear )

Station, Unit No. 1) )

LICENSEE'S TESTIMONY OF WILLIAM E. RIETHLE IN RESPONSE TO CONTENTION NOS. EP-3 (C) (1) & EP-18 3

AND BOARD QUESTION NO. 4 (OFFSITE RADIOLOGICAL MONITORING) -

8102170 35%

TABLE OF CONTENTS

- Page Outline Testimony Introduction..................................... 1

! Response to Contention No. EP-18................. 2 Response to Board Question No. 4 and Contention No . EP-3 (C) (1) . . . . . . . . . . . . . . . . . . . . 9 Table 1 and Figure 1 Table 2 and Figure 2 Statement of Professional Qualifications t

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l OUTLINE This testimony deals with offsite radiological monitoring at Three Mile Island, It addresses Board Question 4 and Con-

tention Nos. EP-3 (C) (1) and EP-18.

In the first part of the testimony the purposes and goals of Licensee's radiological environmental monitoring program

("REMP") are discussed. The basis on which the number and location of sampling sites were chosen is explained. The dosimeters used in the REMP are described and tha program to assure accurate results is presented.

The second part of the testimony addresses the remote read-out, real-time monitoring devices being deployed around TMI.

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INTRODUCTION 1

This testimony, by Mr. William E. Riethle, III, GPU, Manager-Environmental Controls, TMI, is addressed to Contention No. EP-18:

It is contended that the Licensee's environ-mental radiation monitoring program contains an insufficient number of monitoring sites and an inadequate distribution of monitoring sites within twenty miles of the Unit 1 site to provide suffi-cient protection of the public health and safety.

It is further contended that there is in the Licensee's environmental radiation monitoring program an unwarranted reliance on the use of thermoluminescent dosimeters (TLD's) for provid-ing information used to calculate radiation ex-posure data and that this unwarranted reliance on TLD's seriously underestimates radiation doses to the public. It is also contended that the Licensee does not possess adequate portable radiation monitors to provide additional informa-tion in the event of an offsite radiation release, and that the Licensee does not exercise adequate administrative control over the maintenance of these units, nor the training of personnel in their use. It is contended that the radiation monitoring program of the Licensee must be greatly upgraded prior to restart to ensure adequate protection of the public health and safety.

Contention No. EP-3 (C) (1) :

l L The NRC's vague instruction to the licensee to I

" upgrade" in generally unidentified respects its "offsite monitoring capability" is insufficient to assure that such upgrading will result in the ability to obtain and analyze the type and volume of information essential for protection of the public health and safety. ANGRY contends that such capability must at minimum encompass the following elements or their equivalent:

i (1) Permanent offsite monitoring devices which register all forms of ionizing radiation and which can be remotely read onsite.

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and Board Question No. 4 (Tr. 2393): ,

(a) Has the licensee considered stationing a limited number of dose rate meters near the site, with the data telemetered to the control room or the response center?

(b) Has the licensee considered placing meters which publicly measure background radiation levels at a number of public places, thereby enabling the populace to know what the level is?

RESPONSE TO CONTENTION NO. EP-18 BY WITNESS RIETHLE:

Contention No. EP-18 takes issue with Licensee's radiological environmental monitoring program ("REMP") at TMI. It asserts that the REMP contains an insufficient number and inadequate distribut;on of monitoring sites, and that there is an unwar-ranted reliance on the use of thermoluminescent dosimeters

("TLD's"). These matters are addressed in this testimony. The contention also alleges that there is an' inadequate number of portable radiation monitors, that these monitors are not properly maintained, and that personnel are not trained in the use of such monitors. These latter allegations are addressed in " Licensee's Testimony of Robert E. Rogan, George J. Giangi and Alexis Tsaggaris on the Adequacy of Onsite Emergency Preparedness at Three Mile Island, Unit 1," dated-February 9, 1981.

The REMP consists of sampling regimens that provide informa-tion needed to determine whether radiological exposures in the

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environment are within established limits. The program also moniters the long-term buildup of specific radionuclides in the environment in order to assure that such radionuclides do not be-come significant. The program at TMI is designed to monitor the major pathways of exposure to the general populace so as to demon-strate compliance with regulatory guidelines for allowable ex-posures to unrestricted areas. These regulatory guidelines in-clude 10 C.F.R. Part 20, 10 C.F.R. Part 50, Appendix I, and 40 C.F.R. Part 190.

During the operational life of the nuclear generating facility, normal radionuclide releases are monitored through a systematic sampling program which includes air, water, and terrestrial media.

The media chosen for the sampling program reflect the indicator concept of environmental surveillance. In this manner the sampling program gives appropriate consideration to both the critical path-ways of radionuclide transport and the quality of the environment in relation to historical environmental data. The REMP permits quantitative evaluation of radionuclide levels in the environment.

This information is compiled and presented in an cnnual report to the U.S. Nuclear Regulatory Commission, the U.S. Environmental Pro-tection Agency, and the Pennsylvania Bureau of Radiation Protection l

for their review and evaluation.

Prior to March 1979, the RE.iP at TMI conformed to the NRC's position of what constituted an acceptable radiological monitor-ing program as specified in Regulatory Guides 4.1 (Rev. 1) and 4.8. In many instances, the program exceeded the NRC's require-ments, t

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In accordance with emergency response plans, the normal REMP was intensified immediately following the accident at Unit 2. This increase in monitoring regimens during periods of unusual activity I

is a prudent step for evaluating subsequent impacts. A broader data base assists in quantifying what impacts, if any, have occurred.

Such an . Luation, however, is necessarily only as an after-the-fact analysis of what has occurred. That is to say, the radio-1 nuclide deposition already would have to have occurred for environmental samples to reflect qualitative and quantitative data with respect to offsite releases. It is for this reason that during the Unit 2 accident emergency, real-time monitoring teams were dispatched to monitor off site. Information obtained from these teams was utilized for a timely assessment of the accident situation. Data gleaned from the intensified REMP was useful in providing an historical assessment of overall impacts associated with the accident releases. This function is similar to functions performed by the REMP during normal plant operations.

In November 1979, the NRC Staff amended its REMP requirements.

l A Branch Technical Position, revising, in part, Regulatory Guide 4.8, was issued. 71is revision proposed an increase in the number of direct radiation stations required as part of an i

operating facility's REMP. The remainder of Regulatory Guide 4.8 was essentially unchanged, as the review committee adjudged the original requirements to be adequate for their stated purpose.

The REMP at TMI complies with Regulatory Guide 4.8, as amended by the November 1979 Branch Technical Position.

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Station locations for REMP sampling are based on four main criteria: (1) site meteorology; (2) Susquehanna River hydrology; (3) local demography; and (4) differential land usage.

Historical site meteorology data since 1967 has identified four prevailing wind directions: northwest (NW), west northwest (WNW) , west (W), and north northwest (NNW). This information, coupled with the annual average dispersion factor (X/Q), is utill?.ed for sample site locations. In certain instances, sampling points must be located in alternate sites due to local site conditions. For example, although optimal monitoring loca-I tions for air samples may be within a 600 meter radius around TMI, to do so would require placement in the Susquehanna River.

In such instances, the next optimal site is choten for instru-ment placement.

Other monitoring locations are chosen by demography, river hydrology (for water sampling stations) , differential land usage, and special areas of interest. A yearly dairy census is taken around the area to ensure monitoring stations are adequate since changes in dairy herds and commercial practices may suggest cer-tain alterations.

TLD locations were placed primarily or. the NRC's Branch Technical Position recommendations. These recommendations are as follows:

i Forty stations with two or more dosimeters or one instrument for measuring and recording dose rate continuously to be placed as follows: (1) an inner ring of stations in the general arca of the site boundry and an outer ring in the 4-5 mile

range from the site with a station in each sector of each ring (16 sectors x 2 rings = 32 stations).

The balance of the stations, 8, should be placed in special interest areas such as population centers, nearby residences, schools, and in 2 or 3 areas to serve as control stations.

To comply with these recommendations, TMI has 73 stations with two or more dosimeters located as follows: 12 stations are located at or near the site boundry, a second ring of 7 stations is located out to a distance of 0.6 miles from the site. Two l

additional rings comprised of 6 and 2 stations each are found at distances of 1 to 3 miles respectively. The 4-5 mile ring requested by the NRC is composed of 16 stations, ranging in distance from 4.3 miles to 5.0 miles. The remainder of the 30 stations are located in areas of special interests at distances of 5-10 and 10-20 miles from the site. A complete description of the l present REMP sample locations is given in Table 1 and depicted l

I in Figure 1.

At the present time, TMI is utilizing two dosimetry systems.

l The original system is composed of two sets of TLD's which are read monthly and quarterly. Each badge contains fcur areas of readout for gamma radiation. Badges are sent to a commercial laboratory for processing with quality control being maintained by a second independent laboratory. Though not now being used, TMI has the capability to process badges from this. system onsite.

The second system in place is comprised of TLD's with both beta and gamma detection capability. This system is being field tested and environmentally qualified for purposes of replacing 2

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the original TLD system described above. Sensitivity of these badges is in the 1 mR to 1000 R range. With this new system TMI would have complete processing capabilities onsite to facilitate handling and data acquisition. As with the current system, an independent quality control program will be maintained utilizing an independent laboratory.

Standards for the use of TLD's in the environment are set by the NRC (Reg. Gu'de 4.13, Rev. 1) with the assistance of the Health Physics Society Standards Committee of the American National Standards Institute (" ANSI"). These standards specify the minimum acceptable performance of TLD's used for environ-1 mental measurements and outlines methods to test for compliance, procedures for calibration, field application, and reporting. It is a Technical Specification requirement of Unit 1 that environ-mental TLD's comply with these standards. I am unaware of any information showing that TLD's which satisfy these standards underestimate radiation doses to the public.

The Environmental Controls Group is responsible for the TMI REMP. The Group is staffed by twelve professionals whose.responsi-bilities are to maintain both the nonradiological and radiological environmental monitoring programs. To ensure accuracy of RanF sampling, environmental. samples are collected by scientists within the Environmental Controls Group and delivered by these

! individuals to the appropriate analytical laboratory. Ins crumenta-tion is calibrated and routinely surveyed by the staff of the Environmental Controls Group during sampling periods as a safe-guard against malfunction or possible vandalism. Should replace-L

ment be necessary, duplicate instrumentation is maintained.

Audits of commercial laboratories participating in the REMP cnalysis are performed through in-house check proced2res., the U. S. Environmental Protection Agency (" EPA") cross-check pro-gram, quality control comparisons, and visits by the Environmental Controls Group sraff to the laboratories tLamselves. In-house checks are conducted by a careful review and compariron of in-coming data with sample collection sheets, sample procedure review, and historical site data. Anomalies are brought to the atten-tion of the reporting laboratory and reanalysis is conducted if discrepancies cannot be resolved. REMP laboratories also are required to participate in the EPA's intralaboratory comparison program. The results of these comparisons are presented in each REMP annual report. As a third check on the participating labora-tories, a quality control program is conducted. This results in an independent evaluation of the laboratories involved. A final check is provided by Environmental Candrols Group audits of the laboratories, which involve review of laboratory procedures and visits to the laboratories for onsite inspection of analysis pro-cedures. A complete review and audit of all environmental moni-toring data for the year is conducted by the Environmental Con-trols and TMI qu lity assurance groups prior to submittal of the annual report. REMP sample collection data is maintained through retention of collection sheets. The sample collection procedures are reviewed by Environmental Controls' in-house professional staff periodically, to ensure proper up-to-date regimens are followed.

i RESPONSE TO BOARD QUESTION NO. 4 AND CONTENTION NO. EP-3 (C) (1)

BY WITNESS RIETHLE:

Licensee has purchased a real-time environmental radiation rmnitoring system from Reuter-Stokes of Cleveland, Ohio. The system, kncwn as Sentri 1011, consists of low and high level direct radiation sensors, remote station electronics, remote sta-tion transmitters and receiver, and a central processing computer.

Data obtained from the sensors are relayed back to the cen-tral computer via telephona or telemetry communications providing instantaneous dose rate data from each of the remote locations.

The sensors (one low level and one high level sensor at each location) can detect direct radiation in the range of 0 to 500 mR/hr and 500 mR/hr to 10 R/hr for the low and high range sensors, respectively.

Licensee's system will be headquartered at the offices of the TMI Environmental Controls group and is composed of 16 remote stations. Site locations were chosen according to population density, site meteorology, and local topography. Where possible, a remote station will be located within each of the sixteen radial sectors around TMI. The  ; mote stations are equipped with LCD readout panels to allow public access to instantaneous dose rate information. A tentative list of sites (Table 2) and a map indicating locations (Figure 2) are attached.

-While Licensee is installing a real-time environmental radiation monitoring system, I do not believe that such a system is necessary to achieve an adequate state of emergency prepared-

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ness at TMI. As explained in the testimony of Messrs. Rogan, Giangi and Tsaggaris, accideit assessment and protective action recommendations will be based on plant status and offsite dase projections calculated from in-plant effluent monitor readings, as confirmed by mobile offsite radiation monitoring teams. The real-time monitoring system I have described may provide addi-tional data that should be considered during an emergency situa-tion, but that information is not a prerequisite for Licensee fulfilling its emergency planning or environmental monitoring responsibilities.

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TABLE 1 Sampling Locations Samole Identification Metropolitan Edison identifies samples by a three-part code: The f.irst two letters are the power station identification code, in this case TM. The next one-to-three letters are for the media sampled.

AI = Air Iodine ID = Immersion Dose (TLD)

AP = Air Particulates M = Milk AQF = Fish RW = Precipitation ~

AQP = Aquatic Plants . SW = 5.rface Water AQS = Sediment V = Vegetation E = Soil MG = Milk (Goats)

FPF = Fruit EW = Effluent Water FPL = Green Leafy Vegetab'as The last four symbols are a location code based on direction and distance from the site. Of the last four symbols, the first two represent each of the sixteen angular sectors of 22h degrees centered about the l reactor site. Sector one is divided evenly by the north axis and the other sectors are numbered in a clockwise direction; i.e., 2 = NNE, 3 = NE, 4 = ENE, l

5 = E, etc. The next digit is a letter which repres2nts the radial distance l

from the plant:

S' = On-site location E = 4-5 miles off-site A = 0-1 miles off-site F = 5-10 miles off-site B = l-2 miles off-site G = 10-20 miles off-site C = 2-3 miles off-site H = > 20 miles off-site l D = 3-4 miles off-site l

This last number is the station's numerical designation within each

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sector and zone; e.g.,1, 2, .. . 1 1

The location portions of these codes (i.e.,151, 3Al, etc.) are shown 1 ,

in Table A-1 along with detailed information and map coordinate numbers used to designate the individual samples on maps A-1, A-2, and A-3. .

TABLE 1 TAOLE A-1 4

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 5AHrLE LOCAll0NS SAMPLE' LOCATION HAP O!5fANCE l NEOluM CODE NUf18ER (MILES) AllHUTH ,

DESCRIPTION AP.AI,IO 152 1 0.4 0 N of site, North Weather Station 10 252 2 0.7 28 MNE of site on light role in middle of North Bridge 10 452 3 0.3 71 ENE of site on top of d'ke. East Fence 10 552 4 0.2 95 E of site on top of dike. East Fence 10 851 5 0.4 167 $$E of site 10 952 6 0.8 184 5 of sf te at South Beach of Three Mlle Island EW 1051 7 - - On sit 9, RML-7 10 1052 8 0.4 200 55t! f site 1

10 1151 9 0.1 221 SV of site, west of Mechanical Draf t Towers on dike 10 1351 10 0.4 270 W of site on Shelley Island SW 1352 11 0.1 270 W of site, latake i

10 1452 12 0.4 293 WNW of site on $helley Island 10 1551 13 0.5 317 NW of site on Shelley Island 10 1651 14 0.2 340' ilW of site at gate in fence on wst side of Three Mlle Island, North boat dock ACP 1A1 15 0.7 1 N of site A05 1A2 16 0.7 0 N of site at north tip of Three Mlle Island 10 3Al 17- 0.6 35 NE of site on Route 441 I

ID 4Al 18 0.5 65 ENE of site on Laurel Road AP, AI,jtW,l0 SAI 19 0.4 100 E of site on verth side of Observation Center Building 10 6Al 20 0.5 117 ESE of site on light pole on Route 441 AQ5 1Al 21 0.3 137 SE of site 10 7A3 22 0.6 143 SE de ette on Route 441 SW.AQP 9A2 23 0.5 188 5 of site below Olscharge Pipe A35 10A1 24 0.8 202 SSW of site A05 .llAl 25 0.5 225 SW of site 10 11A2 26 0.5 221 SW of site on Beech Island 101 16Al 17 0.4 332 NNW of site on Rohr Island

• m 181 28 1.2 5 N of site. farm along Route 441 M.fPL 4SI 29 1.1 65 EXE of site, farm west of Cringrich Road P. f *'. 783 30 1.6 125 SE of site, fam on the east side of Conewaqo Creek

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• 1.9 163 SSE of site. fal uuth .

1.t,Anf,AQS.AQP 901 31 1.5 178 5 of site above York Haven Dam i MS.1D 1081 32 1.1 2-0 SSW of site on south beach of Shelley Island ID 1101 33 1.9 227 SW of site on Route 262 AP,Al,IO 1281 34 1.6 253 flSW of site adjacent to Fishing Creek, f oldsboro Air Station 10 1381 35 1.2 261 W of site at Goldsboro Marina ID 1481 36 1.4 290 WW of site on Still House Road 10 1581 37 1.8 334 N'J of site on Still House Road AGF 1681 38 1.1 , 337 NfM of site below Fall Island

AP,Al 10 ICI 39 2.6 355 N of site at Middletown Substation SW IC3 40 2.3 347

• N of site at Swatara Creek AP AI.RW,10 801 41 2.3 159 55Dof site at Falmouth-Collins Substation SW 8C2 42 2.3 165 SSE of site. York Haven Hydro M, fPL 1401 43 3.7 283 WNW of site, farn 10 IE4 44 4.3 3 N of site on Vine Street exit from Route 283 10 2El 45 4.8 18 NNE of site, School House Lane and Miller Road 10 3E3 46 4.5 42 NE of site on Rennedy Lane' 13 4E5 47 4.9 62 EHE o' site on Beagle Road 10 5El 48 a 4.6 81 E cr site, North Market Street and Taeger Road ID 6E6 49 4.6 115 ESE of site on Amosite Road e 10 7E6 50 4.8 131 SE of site. Bainbridge and Risser Roads SW 8El 51 4.1 160 55E of site on Brunner Island 10 SE2 52 4.1 155 55E of site at Guard Shack on Brunner Island 10 $El 53 4.9 182 5 of site on Canal Road, Conewago Helghts

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TABLE 2 RD:0TE STATION 1.0t:NrlONS Stetion Un. Sector I.ocation Dist.ince from Site 1 1 Mill Street Substation (Middletowa) 2.5 miles 2 2 North Cate Guard Shack 600.0 meters 3 3 Ceyers Church Substation 1.5 miles 4 4 Alwine Farm 1.5 miles 5 5 Observation Center 800.0 meters 6 6

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500 Substation 1000.0 meters 7 7 Beckers Fara 1.5 miles 8 8&9 South Cate Guard Shack 1.5 miles 4

9 10 Shelley Island 1.25 miles 10 1,2 Coldtboro 1.25 miles ,

11 14 Shelley Island 600.0 meters 12 15 Environmental Controls Center 3.7 miles 13 16 Crawford Station 2.5 miles 14,15,16 - To be determined see accompaning map for location corresponding to sector .

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. sX THREE MILE ISLAND NUCLEAR STATION '

Proposed locations for Environmental Radiation Monitoring Stations (Reuter-Stokes) within 5 miles of the site.

f WILLIAM E. RIETHLE, II!

Business Address: TMI Nuclear Station P.O. Box 480 Middletown, Pennsylvania 17057 Education: B.A., Biology, University of Pennsylvania, 1970.

M.S., Environmental Science, Drexel University, 1972.

, M.S., Health Physics, Rutgers University, 1975.

Experience: Manager, Environmentel Controls TMI; GPU Nuclear, 1979 to present. Responsible for the formation, implementation, and performance of the Company's environmental group at TMI. Responsible for biological and radiological environmental monitoring activities and studies at TMI.

Senior Licensing Engineer; GPU Service Corporation, 1976 to 1979. Performed' environmental licensing and nuclear licensin3 duties for Forked River Nuclear Station, environmental licensing of fossil plants,

! and site selection studies.

Chief Project Licensing Coordinator; Stone &

Webster, Inc., 1976. Performed environmental and nuclear licensing duties for a domestic nuclear power plant.

! Licensing Engineer; Ebasco Services, Inc., 1973 to 1976. Performed environmencal licensing duties for several domestic and foreign nuclear

~

power plants.-

t Head, Radioimmunoassay Laboratory, Nuclear j Medicine Department; Middlesex General Hospital, 1972 to 1973. Responsible for the formation and operation of a radioimmunoassay laboratory.

Research Assistant, Radiation Research Laboratory; Albert Eingtein Medical Center, 1970 to 1972.

Performed experiments in canc_er/ radiation effects area.

Sergeant, U.S. Army Reserves, 1966 to 1972.

Honorable Discharge.

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i Professional Affiliation: American Health Physics Society.

Publicatio.1:

~

" Metropolitan Edison Company's Radiation Environmental Monitoring During Venting of

' TMI-Unit 2 Containment", Transactions of the American Nuclear Society, Volume 35, November 1980.

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