ML20028A229

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Sanitized Version of Investigation & Re-Assessment of Beta & Gamma Radiation Exposure of Auxiliary Operator T on 790328, Revision 1
ML20028A229
Person / Time
Site: Crane 
Issue date: 09/10/1982
From:
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20027D780 List:
References
RTR-NUREG-0600, RTR-NUREG-600 9210-0593, 9210-593, PCI-TR-186A, NUDOCS 8211170103
Download: ML20028A229 (44)
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Text

.

s Licensing i 4410-82-L-0.020 Revision 1 9210-0593 PCI TR-186A September)0,1982 i

1 INVESTIGATION AND RE-ASSESSMENT OF THE i

BETA AND GAMMA RALIATION EXPOSURE OF AUXILIARY OPERATOR "T" ON MARCH 28, 1979

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INVESTICATION AND RE-ASSESSMENT OF THE BETA AND CAMMA RADIATION EXPOSURE OF AUXILIARY OPERATOR "T" ON MARCH 28. 1979 TABLE OF CONTENTS 7

SECTION

.[PAGE S8mmary........................................

1

- 1.

Introduction...................................

2 3

Findings and Discussion........................

3 3

Basic Assumptions for all Dosimetric Models....

4 6

Discussion of Dosimetric Methodology...........

5 6

Conclusions....................................

6 9

Recommendations................................

7 10

Enclosures:

(1) Letter, TMI-II-R-16032, R.C.4.3.2, dated September 25, 1980

Subject:

Airborne Contamination Levels in Aux. Building on March 28, 1979.

(2) Memo to File, dated October 10, 1980

Subject:

Air Submersion Dose Equivalent Rate Estimates for Unit II Aux.

Building Near Radwaste Disposal Control Panel for 1800 on March 28, 1979.

(3) Memo to File, dated October 16, 1980

Subject:

Air Submersion Dose Rate Estimates for Unit II Aux. Building Radwaste Disposal Control Panel, 1810 hours0.0209 days <br />0.503 hours <br />0.00299 weeks <br />6.88705e-4 months <br /> on March 28, 1979.

(4) Memo to File, dated January 14, 1982

Subject:

Beta Depth-Dose Estimates for Unit II Aux. Building Near Radwaste Disposal Control Panel for 1810 on March 28, 1979.

(5) Beta and Gamma Calculations for Aux. Operator "T" (6) Unit II HP Control Point Area TLD Data -- 999-99-9948 Appendices:

(i) Initial Investigation conducted by Met-Ed on April 24, 1980.

(2) Initial Interview of Auxiliary Operator "1" by Gordon M. Lodde and Charles E. Smedley (3) Interview of Auxiliary Operator "T" by S. W. Porter, Jr., of Porter Consultants, Inc.

(4) Letter from Richard W. Dubiel to File, dated July 19, 1979;

Subject:

Dose Evaluation for Personnel TLDs in Storage. Racks During the Accident.

(5) Memorandum from Mike Buring to Sydney W. Porter, September 6, 1980.

- ~.,.

~.- -

c INVESTICATION AND ASSESSMENT OF THE BETA AND GAMMA RADIATION EXPOSURE OF AUXILIARY OPERATOR "T" ON MARCH 28, 1979 1.

Sununary TheconditionsunderwhichAuxiliaryOperator"T"isbelievedt{ohavereceived diisexposureonMarch 28, 1979, were investigated. This was dahe by a combination iof interviews, time-and-motion studies, ganmaa area monitor and survey instrument readings, and comparisons with TLD results from other personnel who entered the same general area at about the same time as Auxiliary Operator "T".

These studies indicate that the exposure in that area could have resulted from two main sources:

(1) highly contaminated liquids in pipes and storage tanks, and (2) airborne radioactive noble gases and particulates. On this basis, calculations 1

were performed to estimate the radioactive nobles gas and particulate concentrations and dose rates at the Radwaste Disposal Control Panel (RWDCP) at the time of his entry. The dose rates were calcula.ted using a semi-infinite cloud model. The results correspond quite well with the gamma dose registered by Auxiliary Operator "T's" TLD. The calculated nonpenetrating dose, however, was found to be much lower than that registered by Auxiliary Operator "T's" TLD. Many attempts were made to explain this difference, but none were entirely successful mainly because of inadequate data on the response of the Harshaw TLD under certain irradiation conditions. One possible explanation for the high registered nonpenetrating dose is that at Icast some of it may actually be due to low-energy photons rather than electrons. Xe-133 was the major noble gas component of the mix in the air at the time of entry. This radionuclide emits an 81 kev gamma with an abundance of N37% and 30 kev x-rays with an abundance of 38%, plus a 35 kev x-ray with an

. abundance of 48.8%.

The response of the Harshaw TLD to photons is calibrated at Cs-137 energy; and therefore, it is to be expected that the factors derived at 662 kev would not apply well at 81 and at 30 kev. It is possible, and even likely, that an undetermined fraction of the gamma-corrected beta chip reading i,

i 10 due to lower ensrgy photen from the inctspic cixtura cf noble gtses.

Even though the low energy photons will contribute.to the nonpenetrating dose, it is felt that a beta factor of 4 is appropriate when estimating the i

nonpenetrating dose from the isotopic mixture of noble gases. pincenoble 1

1

.3ases can easily penetrate or diffuse into the TLD badge and prgtective clothing, i

ftheir protection factor is of questionable value when assessing the dose to the skin. Because of the large uncertainties associated with the reported TLD values, these uncertainties cannot be reduced without an inordinate amount of experimental work; therefore, the reported TLD chip readings probably represent a reasonable upper limit of the skin dose.

Summary of Auxiliary Operator "T's" Dose Dosimetric Model F'

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i

- Dosimetric Model D Dosimetric Model E (Reasonable upper (Time-and-Motion)

(Time-and-Motion)

Limit) l Whole Body y............

1.4 rads.......... I.4 rads.........

1.4 rads

+

Skin S 2

rads.........

3.7 rads........

10.8 rads J

Total Skin..............

3.4 rads..........

5.1 rads........

12.2 rads 4

In essence, therefore, the gamma and beta dose should be assigned on the basis of the TLD readings and the assumption that these readings were caused by high-i l

energy (over 100 kev) photons and beta radiation. The resulting doses are 1.4 l

rads whole body and 12.2 rads to the uncovered portion of the skin of the back i

j of the head. A review of actual individual TLD chip reads for individuals who l

were known to have entered the Unit II Auxiliary Building on March 28, 1979, l

indicated an average Chip 1/ Chip 2 ratio of 1.35 1 0.35:1, whereas, Auxiliary Operator "T's" TLD showed a chip ratio of about 3:1. Therefore, it is concluded that personnel who entered the Auxiliary Building during the late af ternoon and I

evening of March 28, 1979, may have been exposed to high levels of nonpenetrating i

I radiation most probably from airborne noble gases. The protective clothing worn may not have reduced the nonpenetrating dose to the skin of the whole body j

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i because of diffusion of the noble gases through protective clothing' demonstrates the attenuation that would be expected under various mass-thicknesses of protective clothing if diffusion of the noble gases does not occur.

2.

INTRODUCTION q

4saresultoftheTMIDosimetryGroup'sretrospectiveinvestihjtionsofearly

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dosimetry records for individuals who were exposed due to the Unit II accident of March 28, 1979, an apparent high beta exposure was identified on April 14, 1980, (see Appendix 1).

It was also noted that several TLDs had been processed manually and only the reading of the deep chip was recorded; therefore, it is possible that other individuals may have received high beta exposure to the skin from noble gases.

Each individual case has been evaluated.

In an attempt to understand Operator "T's" exposure environment on March 28, 1979, several dosimetric models were carefully constructed and compared to known data and time-and-motion studies in order to best estimate his exposure. Although there are six (6) dosimetric models described herein, five (5) models are based on semi-infinite cloud calculations and one is based entirely upon' the TLD nonocoulomb readings. The five (5) models were compared to known data and time-and-motion studies to best estimate his dose.

It was concluded that none of the dosimetric models would explain his nonpenetrating dose; however, his gamma dose could be determined from estimated noble gas concentrations and time-and-motion studies.

3.

FINDINGS AND DISCUSSIONS A.

Interviews were conducted with Auxiliary Operator "T" to determine his activities during the period March 28 - 29, 1979, which may have lead to his suspected overexposure to ionizing radiation (see Appendices 1, 2, and 3).

B.

Written radiation survey records are not available for the period 0400-2400, March 28, 1979; therefore, NUREG-0600 was reviewed, discussions / interviews were held with a number of individuals, and selected NRC interviews were read to provide the best_information as to the radiation levels that may

have existed at the time Auxiliary Operator T entered the Unit II Auxiliary Building at the 305' elevation at about 2120 on March 28, 1979. The following summarizes the available survey data:

(1) At about 1300 on March 28, 1979, the general area exposure rate near

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the Radwaste Disposal Control Panel (RWDCP) was about 8 - 10 R/hr (sce i

Page 11-3-50, NUREG-0600).

(2) HPR-232 readings verified that exposure rates were about 6 - 10 R/hr near the RWDCP during the period 1800 - 2100 on March 28, 1979.

(3) At about 2100 on March 28, 1979, the exposure rate,inside the entrance i

to the 305' elevation of the Auxiliary Building was about 20 R/hr and about 10 R/hr at the RWDCP (see Pages II-3-54 and II-3-55, NUREG-0600).

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C.

Based upon a review of time-and-motion study and calculations based upon measured gamma radiation exposure rates, it is possible to estimate Auxiliary Operator "T's" gamma dose. The estimated gamma dose of Auxiliary "T" from radiation survey data and time-and-motion study is as follows:

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l (1) With a self-contained breathing apparatus, assume that Auxiliary Operator "T" walked from the entrance of the Unit II Auxiliary Building t

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to the RWDCP at an average velocity of two (2) miles hr or

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2.98 ft sec The distance is approximately 240 feet and the' average

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l gamma radiation field was approximately 4R hr ; therefore, his gamma dose was approximately 179 mrads for going to and returning from the RWDCP.

(2) The duration of time spent at the Unit II RWDCP was approximately five (5) minutes and the gamma radiation field at this location was approximately

-1 14R hr ; therefore, his gamma dose was approximately 1.17 rads at this location.

i (3) The duration of time spent near the Unit II primary sample lines, located in the 306' elevation of the Fuel Receipt area, was approximately 1 - 1.5 minutes. Exposure rate was approximately 50 mR/ minute; therefore, his dose was approximately 51 mrads.

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5-(4) Total gamma dose from the time-and-motion study is approximately 1.4 rads. This value agrees with his reported TLD gamma reading of 1.4 rads.

(5) Since the survey instruments used to measure the radiation fields had t

been calibrated to Cs-137 (662 kev) energy, the instrdhents most probably e

overresponded to the isotopic mixture. Therefore, adjustments of the i

isotopic mixture have been made to give a gamma dose rate comparable to survey / monitor reading corrected for a 30% measurement error.

(6) Since there are no beta dose rate measurements recorded, it is not possible to reconstruct the beta dose from the time-and-motion study; however, it is possible to estimate the beta dose from the data in Enclosures 2, 3, and 4.

D.

Although the results of the Unit II KWDCP area TLD for the period of March 1 - 31, 1979, cannot be located, the results of the Unit II HP Control Point Area TLD for the above period demonstrated an actual TLD Chip 1/ Chip 2 ratio of about 2.84:1 for a beta / gamma ratio of 6.8:1 when a beta factor of 4 is used for an exposure to fission gases (see Enclosure 6).

This ratio compares well with the actual TLD Chip 1/ Chip 2 ratio of about 3:1 for a beta / gamma ratio of 7.7:1 for Auxiliary Operator "T's" TLD for the period of March 28, 1979 (see Enclosure 5).

Since the average actual TLD Chip 1/ Chip 2 ratio was about 1.35:1 for individuals known to have entered the Unit II Auxiliary Building on March 28, 1979, it appears that it is highly probable that Auxiliary Operator "T" wore his TLD outside his protective clothing which would result in a nonpenetrating dose of about 2 to 3.7 rads to the exposed skin of the whole body, depending on the dosimetric model used in the calculation and not considering the diffusion of the noble gases through the protective clothing.

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4.

BASIC ASSUMPTIONS FOR ALL DOSIMETRIC MODELS A.

The Primary source of the exposure of Auxiliary Operator "T",was from noble gases released into the Unit II Auxiliary Building from thcise noble gases f

entrained in the water which was transferred to the Auxiliary Building on i

March 28, 1979.

B.

Auxiliary Operator "T's" TLD was most probably worn outside a wet suit during his entry into the Auxiliary Building on March 28, 1979.

C.

The TLD Badge No. 300631 worn by Auxiliary Operator "T" was responding properly. Even though this specific TLD cannot be located to verify its calibration, the history of the TLD from February 1976 through November 1979 indicates that it responded properly to known radiation levels with no known calibration problems.

5.

DISCUSSIONS OF DOSIMETRIC METHODOLOGY A.

General (1) Since one of the basic assumptions was that the primary sources of Auxiliary Operator "T's" exposure was from noble gases released into the Unit II Auxiliary Building and since there is no grab sample data available as to airborne mix and concentration of noble gases, it was necessary to estimate airborne concentrations of noble gases at the time of Auxiliary Operator "T's" entry into the Auxiliary Building between 1800 - 2100 on March 28, 1979.

(2) Enclosure 1 describes the methodology (B&W revised ORIGEN Code named LOR-2) used in estimating the airborne concentrations of noble gases present near the Radwaste Disposal Control Panel at the time of Auxiliary Operator "T's" entry. The noble gas dose rate conversion factors (DRCFs) in Table B-1 of NRC Regulatory Guide 1.109 were used to l

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calculate the gamma dose rates in air from the isotopic mixture in and then proportioning the concentrations of the isotopic mixture to give a gamma dose rate which corresponded to Teletector and s.

remote area gamma monitor readings after these values 1rere-corrected for

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s energy response of the detectors.

4 B.

Specific Details (1) The first dosimetric model (Model A) utilized DRCFs for beta skin and gamma whole body from Table B-1 of NRC Regulatory Guide 1.109 and the adjusted airborne radionuclide concentrations. For exposure to a semi-infinite cloud of noble gas, the total body dose from external 2

radiation was determined at a depth of 5 cm (5E3 mg/cm ) and the skin dose 2

at a depth of 7E-3 cm (7 mg/cm ) (see Enclosure 2).

The major uncertainty factor with this Model is in the calculation that must be made to attenuate the betas through the protective clothing worn by Auxiliary Operator "T".

(2) Dosimetric Model B involved using the DRCFs from WASH-1258 and BNWL-1754 and the adjusted airborne radionuclide concentrations. For i

exposure to a semi-infinite cloud of noble gas, the total body dose from external radiation was determined at a depth of 5 cm (SE3 mg/cm )

2 and the skin dose at a depth of 7E-3 cm (7 mg/cm ) (see Enclosure 3).

l The major uncertainty factor with this Model is in the calculations that must be made to attenuate the betas through the protective clothing worn by Auxiliary Operator "T".

(3) Dosimetric Model C utilized beta depth-dose calculations under 0, 5, 2

50, and 100 mg/cm. With this Model the assumption was a semi-infinite air source medium and a tissue-equivalent target medium and the adjusted airborne radionuclide concentration (see Enclosure 4). The major problem with this Model is that there is only an indirect method of

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calculating the gamma contribution to the skin dose by using another model.

(4) Dosimetric Model D utilized the beta depth-dose calculdted by Dosimetric 1

i Model C (see Enclosure 4) plus the gamma dose calculat&d by Dosimetric 8

Model A (see Enclosure 2), and the time-and-motion stu2y to give a total 2

nonpenetrating dose under 5 mg/cm absorber. Model D was used because it is more representative of the actual conditions under which Auxiliary Operator "T's" TLD was most probably exposed. This Model utilizes the gamma and total nonpenetrating dose calculated from the time-and-motion study.

(5) Dosimetric Model E makes the assumption that Auxiliary Operator "T's" TLD was responding properly to gamma radiation; therefore, the

.nanocoulomb readings from the TLD gamma chip could be used to calculate the gamma dose. This Model utilizes the gamma dose from the TLD and the total nonpenetrating dose calculated from the time-and-motion study and the beta dose rate from Dosimetric Model B.

(6) Dosimetric Model F also makes the assumption that Auxiliary Operator "T's" TLD was responding properly; therefore, the nanocoulomb readings from the TLD chips could be used to calculate the skin dose. The major uncertainty factors with this Model are the beta factor that is used to calculate the beta dose, and the response of the TLD to low-energy photons.

Since the beta energies of the isotopic mixture of the noble gases is sLailar to the uranium slab beta energies, it is therefore reasonable to use a beta factor of 4 when calculating the beta dose.

The method employed in the calculations was taken from HP-1642, which was in effect at the time of the suspected exposure (see Enclosure 5).

This Model corresponds to the third basic assumption (see Page 6).

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CONCLUSIONS A.

Based upon the findings, Auxiliary Operator "T" was exposed.,to a cloud of noble gases in the Auxiliary Building as well as fixed sources f

during his activities on March 28, 1979.

4B.

Based upon the findings, it is possible to reconstruct Auxiliary Operator "T's" gn=a dose, but it is not possible to reconstruct his beta dose.

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C.

Based upon available information/ records, Auxiliary Operator "T's" TLD was functioning properly.

D.

Based upon Dosimetric Model F, Auxiliary Operator "T" received an upper limit dose to the uncovered head of 10.8 rads beta plus 1.4 rads ga - a, or a total dose of approximately 12.2 rads during his activities on March 28, 1979, as measured by his TLD.

E.

Based upon available information/ records, Auxiliary Operator "T's" occupational dose for the first calendar quarter of 1979 is as follows:

(1)

Sim==ary of Auxiliary Operator "T's" radiation exposure, first calendar quarter 1979 MRAD WHOLE BODY MRAD SKIN OF HEAD MRAD SKIN PERIOD GAMMA BETA OF HEAD 1/1/ 7 9 - 1/ 31/ 7 9.........

35.............. 0........... 35 2/1/ 7 9 - 2/28/ 7 9......... 20.............. 0........... 20 l

3/1/79 - 3/28/79.......

1000.............. 0.........

1000 I

i 3/28/79 - 3/29/79...... 1400.......... 10,800.......

12,200 3/29/79 - 3/31/79.........

0.............. 0............. O l

First Quarter........ 2,455.........

10,800....... 13,255 (2) Auxiliary Operator "T's" skin of the whole body radiation dose is 2.5 rads gamma plus 10.8 rads beta, or approximately 13.3 rads to the skin of the head.

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7.

RECOMMENDATIONS It is reconnended that the doses in Section 6.E. above be assigned to 'the J.

official First Calendar Quarter 1979 Dosimetry Record of Auxiliary Operator t.

"T" 1

A copy of this report should be submitted to the NRC as required by 10 CFR 20.405.

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INVESTIGATION AND ASSESSMENT OF THE BETA AED GAMMA RADIATION EXPOSURE OF AUXILIARY OPERATOR "I" ON MARCH 28, 1979 7,

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ENCLOSURES e

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, i.r<a.ownl.1 7:a.il L.10vis KC 4 4. 3 2 -

.' ; - METROPOLITAN EDISON COMPANY se a

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subject Airborne Contamination Levels in Aux.

Location THI-II Building on March 28, 1979 Dstr '.

September 25,

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To

..G. Lodde

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Per your request, the Radiological Analysis Group has completed an analysis in an attemst to quantify the airborne concentrations near the ltadwasta Panel (305'el) on March 28, 1979.

The purpose of this calculation was to determine a source term for personnel exposure during the hours of 1800 thru 1900.

The estimated concentrations' of radionuclides near the Radwaste Panel were as follows:

ESTIMATED AIRBORNE ACTIVITY NEAR RADWASTE PANEL (3/28/79)

Time:

1710_

. Time:

1810 Time:

1910 ISOTOPE pCi/cc yCi/cc pCi/cc Kr-83m 2.3 x 10-3 2.66 x 10~0 8.34 x 10-6 Kr-85m 1.23 x 10-1 4.52 x 10-2 1.04 x 10-2 3.'12 x 10~3 2.56 x 10-3 2.55 x 10-3 Kr'85 Kr-88 8.95 x 10-2 1.96 x 10-2 1.94 x 10~3 Rb-88 4.51 x 10-2 6.01 x 10~3 7.19 x 10-4 I-133 1.52 x 10-5 1.05 x 10-5 7.64 x 10-6 6.01 x 10~1 4.60 x 10-1 4.09 x 10-1 Xe-133m Xe-133 4.50 3.59 3.39 7.09 x 10-0 3.22 x 10-5 2.07 x 10~7 Kr-87 1.31 x 10-2 1.05 x 10-2 1.03 x 10-2 Xe-131m 2.63 x 10-5 2.28 x 10.-7 7.91 x 10-8 Xes135m Xe-135 S.43 x 10~1 4.60 x 10-1 2.26 x 10-1 As you can see, the daughter of Kr-88, Rb-88, is in sufficient These concentration to provide a measurable beta dose.

concentrations are due to the fact that the Aux. Bldg.

ventilation was off during the period from 1530 to 1630, allowing gaseous fission products to accteulate in the buildi.g.

When the ventilation came back on, it took several hours to stabilize the gaseous ' radionuclides.

Continued.

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Airborne Contaminatien Levels in Aux. -Building cn March 28, 1979 September 26, 1980 Page 2 The computer code RADTRhN, a time dependent fission

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product transport code, was used to calculate these values using the source isotopic inventory caTeulated by ORIGEN (Version 2), which B & W has modified and

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named LOR 2.

The TMI-2 core inventory was calculated i

using the appropriate power history and boron concentration history for TMI-2.

The initial conditions were 83,000 kg U with an average enrichment of 2.63 w/o U-235, and final burnup of 3175 MWD /MTU (95 EFFD).

g This data was used as input to the RADTRAN code, which decayed the fission, products to the time of cladding failure (+130 minutes) and then calculated the concentration The first RCS sample in the RCS as a function of time.

(drawn at 6:46 a.m.) is in good agreement (s87. for I-131) with the calculated values of RADTRAN for non-gaseous The first sample was not pressurized and, therefore isotopes.

not representative of gaseous concentrations.

The concentration of the water transferred to the Aux.

Building was calculated using current data on mass balances,

e.g., letdown rate, reactor building sprays, opening of PORV, sump pump operation, etc.

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It is' interesting to note that these calculations indica'ted' the Aux. Sump overflowed at. +7:45, which correllates almost c..

exactly with Aux. Building mo'nitor HP-R3236 rapid increase.

The building ventilation system was modeled for known on/off periods of operation.

'In su= mary, this analysis.has shown a mechanism for an airborne beta-emitting nuclide of 5 Mev (max) to be present The actual in Aux. Building during.the time of interest.

concentration will.naver be clearly known, since there are For this reason, it is recommended that so many variables.

the response of a TLD to a 5 Mev beta be evaluated, and whole body dose be calculated accordingly.

F71IJb

/ K. Schlomer N

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Ap. proved: (Ci

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hanager, Rac,iological Analysis EAS:.JAD:plz cc:

P. E..Ruhter

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Am oemon t. p A.19003 2164948383 i

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octobar 10, 1980 i

TO:

File TROM:

Gordon M. Lodde Air Submersion Dose Equivalent Rate Estimates for Unit TI Aux.' Building

SUBJECT:

Near Radwaste Disposal Control Panel for 1810 on March 28, 1979 REF:

Memo. of September 25,1980 (TMI-II-R-16023) to Cordon Lodde from E. A.

Schlomer and J. A. Daniel entitled " Airborne Contamination 1,evels in Aux. Building on March 28, 1979" 1)

Enclosed is a table summarizing the skin and abole body dose equivalent rates based on radionuclide concentration provided in the above subject reference, af ter adjustments have been mpde to correspond to Teletector and remote area gamma monitor readings. 4 2)

.A brief description of methodology used in the calculation of these dose equivalent estimates follows:

The methodology utilized the dose-rate conversion factors (DRCTs) a)

which were derived from NRC Reg. Guide 1.109, and WASH-1258/B5'L-1754.

b)

The DRCTs wer's converted to (arem/hr per UCi/ce), then multiplying 1810 on the DRCFs by the estimated radionuclide concestration at March 28, 1979 to give skin dose equivalent rates under 7 mg/c=2 i

2 (7E-3 cm) and whole-body dose equivalent rate under 5 g/cm (5 cm).

The DRCTs are for total imersion in a semi-inifinite noble gas cloud.

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Gordon M. Lodde

-CML/sa Attac}iment l

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REV 1 01/14/82 o

SUBMERSION DOSE EQUIVALENT RATES BASED ON ESTIMATED RADIONUCLIDE CONCENTRATIONS AT 1810 ON MARCH 28, 1979

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305" ELEVATION OF AUX. BUILDING a-8-

CONCENTRATION S DRCF S SKIN DOSE Y DRCF Y W.B. DOSE RADIONUCLIDE (pCi/cc)

Skin *

(arem/hr)

Whole Body *

(area /hr)

I.

i 8.62E0 1.15E-4 Kr-83m 1.33E-5 Kr-85m 2.26E-3 1.66E5 3.75E2 1.33E5 3.0E2 Kr-85 1.28E-4 1.53E5 1.96El 1.84E3 2.36E-1 Kr-87,

1. 61 E-6 1.11E6 1.79E0 6.75ES 1.09E0 Kr-88 9.8E-4 2.70E5 2.65E2 1.68E6 1.65E3 Xe-131m 5.25E-4 5.43E4 2.85El 1.04E4 5.46E0 i

Xe-133m 2.30E-2 1.13E5 2.6E3 2.86E4 6.58E2 Xe-133 1.8E-1 3.49E4 6.3E3 3.35E4 6.03E3 Xe-135m 1.14 E-8 8.11E4 9.25E-4 3.56E5 4.06E-3 Xe-135 2.3E-2 2.1ES 4.86E3 2.06ES 4.74E3 i

j Rb-88**

3.0E-4 2.7E6**

8.1E2 5.6E5**

1.68E2 g

I-133**

5.25E-6 8.8E5**

4.62E0 4.4E5**

2.31E0 i

t.

i' 1.53E4 mrem /hr 1.36E4 mrem /hr l-or or 1.53E1 rem /hr 1.36El rem /hr c..

    • Wash 1258 and BNWL-1754 (DCRF = mrem /hr per pCi/cc) l l.i' l

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ENb 8SURE 3*

..Partcr Osnt,ultants, lec.

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.acensome,ea.ioons zissee sas E.

October,16, 1980 70:

File FROM:

John Sykes III

SUBJECT:

Air Submersion Dose Rate Estimates for Unit II Aux. Building Rad-Waste Panel,1810 hours0.0209 days <br />0.503 hours <br />0.00299 weeks <br />6.88705e-4 months <br /> on March 28, 1979 REF:

' Memo of September 25,1980 (1MI-II-R-16023) to Cordon M. Lodde from E. A.

Schlomer and J. A. Daniel entitled " Airborne Contamination Levels in Aux.

Building on March 28, 1979" o

1)

Enclosed is a table summarizing the skin dose and whole-body dose rate estimates based on concentrations provided in the above subject reference, after adjustments have been made to correspond to Teletector and remote area gamma monitor readings. A brief description of the methodology used to calculate these estimates follows.

2)

. Description of Methodology:

a)

The procedure used utilized a modified version of an existing Perter Consultants Inc. computer program (re-named AUZILIAR(Y)) based on Dose Conversion Factors (DCFs) contained in WASE-1258 and BhvL-1754.

b)

The DCFs must be converted to unics" of (ares /hr per }lci/cc) prior to loading into the program.

l c)

The DCTs are multiplied by the radionuclide concentration to give Skin t

2 Dose Rates (defined as the dose rate at 7 ag/cm ) and Whole-Body Dose l

Rates (defined as the dose rate at 5g/cm ).

DCTs are for total 2

i=nersion in a semi-infinite cloud.

d)

The Skin Dose Rates and Whole-Body Dose Rates for each radionuclide were then summed to obtain the Total Skin Dose Rate.(reported in rem /hr) and Total Whole Body Dose Rate (reported in rem /hr).

e)

Finally, the Total Dose Rates were divided by the Total Concentration of radionuclides to obtain a normalized dose rate conversion factor for the particular radionuclide mixture.

i 0e a s.

22C.

re57 = 27 2

h:,ent

1 iT

, DOSE RATES FROM AUXILIARY BUILDING MIX 18*10 HOURS, MARCH,.28,,1979 Q

g.'

a EI DCF-SKIH SKIH DOSE DCF-U.B.

U.B. DOSE CONCENTRATION (MREM /HR)

RATE (MREM /HR)

RATE NUCLIDE UCI/CC

/(UCI/CC)

MREM /HR

/(UCI/CC)

MREM /HR 3

KR83M 1.33D-05

~

7.60D 02 1.01D-02 0.0 0.0 KRBSM 2.26D-03 3.20D'05 7.~23D 02 1.30D 05 2.94D 02 KR85 1.28D-04 1.60D 05 2.05D 01 2.20D 03 2.82D-01

.KR87 1.61D-06 2.70D 06 4.35D 00 1.30D 06 2.09D 00 KR88 9.80D-04 2.00D 06 1.96D 03 1.50D 06 1.47D 03 RB88 3.00D-04 2.70D 06 8.10D 02 5.60D 05

. 1.68D 02 I133 0.0

-8.80D 05 0.0 4.40D 05 0.0 l

XE131M 5.25D-04 4.80D 04 2.52D 01 2.80D 03 1.47D 00 4-XE133M.

2.30D-02 6.00D 04 1.38D 03 2.70D 04 6.2iD 02 XE133 1.80D-01 6.90D 04 1.24D 04 2.50D 04 4.50D 03 l

XE135M 1.14D-08 5.00D 05 5.70D-03 3.50D 05 3.99D-03 XE135 2.30D-02 4.90D 05 1.13D 04 2.10D 05 4.83D 03 TOTAL SKIN TOTAL U.B.

TOTAL DOSE RATE DOSE RATE CONC. = 2.30D-01 REM /HR = 2.86D 01 REM /HR = 1.19D 01 DOSE RATE CONUERSION i

FACTORS FOR MIXTURE:

TOTAL SKIH TOTAL U.B.

' r..

j (REM /HR)/(UCI/CC)

DOSE RATE = 1.24D 02 DOSE RATE = 5.1GD 01 NOTE DOSE CONUERSION FACTORS ARE DERIVED FROM UASH-1258/BHUL-1754.

i 1

ENCLOSURE 4

+

I. '

Jcnuary 14, 1982

\\

1 d

i TO:

File

/

FROM:

Gordon M. Lodde

SUBJECT:

Beta Depth Dose Estimates for Unit II Aux. Building Near Radwaste Disposal Control Panel for 1810 on March 28, 1979 REF:

Memo of September 25,1980 (TMI-II-R-16023) to Gordon Lodde from E. A.

Schlomer and J. A. Daniel entitled " Airborne Contamination Levels in Aux. Building on March 28, 1979"

1) Enclosed are tables summarizing beta depth dose based on radionuclide concentrations provided in the above subject reference, after adjustments have been made to correspond to Teletector and remote area gamma monitor readings.
2) The methodology utilized the depth dose conversion factor from Mart n J.' t i

Berger's article in the Health Physics Journal, Vol. 26 No. 1, pan &. -

1-12 (1974) entitled " Beta-Ray Dose in Tissue-Equivalent Material Irimersed in a Radioactive Cloud".

_s Gordon M. Lodde Health Physics, Consultant Porter Consultants, Inc.

GML/ted Attachments e

G 1+

i

Enciscura 4 B NA. DOSE RATES FOR ESTIMATED AIRBORNE CONCENTRATIONS AT 1810 ON MARCH.28, 1979 305' ELEVATION OF AUX BUILDING

(

CONCENTRATION 6 DRCF FOR

- S DOSE RATE FOR RADIONUOLIDE (uci/cc)

%5mg/cm2 N5mg/cm2 Kr-83m 1.33E-5 Kr-85m 2.26E-3 2.12E5 4.79E2 Kr-85 1.28E-4 1.84E5 2.36El Kr-87 1.61E-6 1.28E6 2.06E0 Kr-88 9.8E-4 3.18E5 3.12E2 Xe-131m

5. 25 E-4 7.19E4 3.77El Xe-133m 2.3E-2 1.29ES 2.97E2 Xe-133 1.8E-1 4.77E4 8.59E3 1.14 E-8 8.37E4 9.54E-4 Xe-135m Xe-135 2.3E-2 2.55E5 5.87E3 Rb-88
3. 0E-4 2E6 6E2 1.62E4 mrad /hr or 1.62E1 rad /hr S DRCFs are in mrad /hr per pCi/cc @ 200C.

e i

i e

n

'., t.

..., e

't-BETA DOSE' RATES FDR ESTINATED ATRBORNE CONCENTRATIONS AT 1810 ON MARCH 28, 1979 305' ELEVATION OF Al'X. BUILDINC 6

CONCENTRATION

% OF S DRCF FOR S DOSE RATE S DRCF FOR S DOSE RATE S DRCF FOR S DOSE RATE it0NUCLIDE (leC1/cc)

MIX 0 mg/cm** AT SURFACE 50 mg/ca'*

UNDER 50 mg/cm 100 mg/cm** UNDER 100 mg/ca' 8

Kr-83m 1.33E-5 0.006 3.61E4 4.8E-1 Kr-85m

- 2.26E-3

.98 2.77E5 6.26E2 4.46E4~

1.01E2 7.82E3 1.77El Kr-85 1.28E-4 0.056 2.3E5 2.94Et 5.33E4 6.82E0 1.43E4 1.83E0 Kr-87 1.61E-6 6.99E-4 1.31E6 2.llEO 9.72E5 1.56ED 7.71ES

't.24E0 Kr-88 9.8E-4 0.43 3.74E5 3.67E2 1.71E5 1.68E2 1.2285 1.2E2 C X2-131m 5.25E-4 0.23 1.44E5 7.56El Xa-133m 2.3E-2 9.99 1.91E5 4.39E3 1.04E2 2.39E0 X:r-133 1.8E-1 78.19 1.36E5 2.44E4

,2.77E2 4.9981 X2-135m 1.14E-8 4.95E-6 9.48E4 1.08E-3 3.43E4 3.91E-4 7.44E3 8.44E-5 XP-135 2.3E-2 9.99 3.16E5 7.27E3 7.74E4

  • 1.78E3 2.37E4 5.45E2 Rie-88 3.0E-4 0.33 2.01E6 6.02E2 1.65E6 4.95E2 1.4E6 4.3882

~

3.78E4 mead /hr 2.60E3 mead /hr

'. i.-.. 1.12E3 stad/h'r 2.09E-2 AvR.

or or or U "**

3.78El rad /hr 2.60E0 rad /hr 1.12E0 rad /hr A l lii:t:FM sire in mrad /hr per lect /cc at 20' C l

s gm e,

e e

,oa,.

,a

.. ~.., ~.

t..

.' P5tter 'Csnr,ultants, Icc.

76 C8118 esseDUSE Pl. ACE

'. ' ARDadong. P A.19003 e

296494 S383 BETA and CAMMA DOSE CALCUIATIONS FOR AUX. OPERAftB 1.

Beta and gansna dose for Aux. Operator "T" was calculated from TIT printout of TLD number 300631 for the period March 28, 1979. TLD ntsaber 300631 was read at approximately 2000 on March 28, 1979:

4300 beta chip 1400 gamma chip The beta dose is:

beta dose =

4300 - (1.15 x 1400) x4 beta dose = 10,760 mrad the gansna dose = 1400 arem,.:

the beta / gamma ratio -7.7 2.

See attached TIT nanocolcunb printout.

l t

e

M.,;'s. :e h.

l*

I-t r*

.sRK O 9 30 0 0 2 8693 0 0 3005

.0. 01 C 11.2.. 2.8 619.il.:. 4. 4 0 0 042 0 3974!'l 2 3255 'l 0 100800

'O 2336i!

.2 221,5'l 0 100396 V*

HI'0602b 2 0 532 i,l -

1

.0 190248 l

g O 0718"I 2 07.1,6

0'200763

~

~

10 0227 2 i2 0172 @ 0.300302

~

0-2178*1.'2 1972 -d.. 0 10 0375

.029800 I '2 0663 !!

0.300800 0' 0292' ly2 026211 0 300030 G-9944-t 0 7326 1 2 6500 1

    • ~

~ ~ ' '#

10'.8'388U1'# * $!'5 0 6.'3'.!! '70<.10 0077 0 0900'1 2 0652 11- 0.300765

... 'O 1037.'l 2 1022 '1 O'.300761 0 06681 1 2 0 5 6 6.'1 "O 100332 30'0402)1. 2 0400 3

.0 300988 0 0 3 6 2'.i !

.2 0349'l 0 100257~

'OO1.64$.F.

2 0346 h 0*10053E 30 2405;i'i 2 23!0 J

.0 100010 8 0 0911l l 2 0915 1 0 300821 r 00923.' 1 2 0773,1 0 100340 0 491611 l2 449.6 1 0 200186 0 0384j1 12 0355 1 ~.0 300965

'O 4258!!

2 4146 1 0 300756

)

s q-O30063h b

10O 2 0120 0 0462: 1 2 0356 1 0 100715' 10 1786l 1 2 1621 1 0*300663 0 06373 3 2 0645 1

'O 3007478

'O 3521,* 1 2 1388 1

.0 100098 70 5693 1 2 5'431 1 10 0624 1 2 1561 1 0 300764 0 1019l 1 2 0'781 1 0 300629. "

O'2139.3

2. 2110 1 0 100092 -

2 0598'1

  • 0 300789 :
  • O 0599j' 1 0 0744: 1 2*1299 3 0 300748 -

0 0742j !

2 0729 1 0 300804 FO 0 1'1 3 2 2012002 a 2 004'

.02266l1 2 2154 1

.0 200394

) 2012 1 2 1837 1 0 100007

  • 0 0752 1 2 0660 1 0 300767 l

3 J 7867,1 2 7589 1 0 100'197 a

0.0754'3 2 9717 f 0 300763 0 0700, 1 2 0639 1 0 3008067 0 0384*3 2 0353 1 0 300984.,

l0 1700 I 2 1603 1 0 100213 0 2t 62 1 2 2427 0 300632, 0 0161 2 2 0160 0 100584, 0 0434 1 2 0315 l' 0 300968 0 0727 3 2 0765 1 0 300760 0 1849' 3 2 1264 1 0 300589!

.0 0742 1 2 0596 1 0 300770 -

08687 1 2 6323 1 0 360584

. m r P

=

i Portet Cencultants, Icc.

13 h8T.Tt ****0V*.E FLt ct t.

6CDMORE,P A.19003 sise n sasa e

~

999-99-9948 UNIT II EP CONTROL POINT AREA TIE DATA -

Time:

1/1/ - 1/31/79 Badge No:

410073 Dose:

0.01 rem gasuna Time:

2/1 - 2/28/79 Badge No:

410073 o

,/

Dose:

0.02 rem gama Time':

3/1 - 3/31/79 e

i Badge No:

410073 1.08 rem gama 7.3 rad beta, beta /samma - approximately 6.8 Dese:

Time:

4/1 - 4/26/79 Badge No; 410073 Dose:

0.000 6

Enclosure v

e l

l l

- ~-

-e-f,

,s INVESTICATION AND ASSESSMENT CF THE BETA AND GAMMA

= RADIATION EXPOSURE OF AUXILIARY. OPERATOR "T" ON MARCH 28, 1979 e

9 i-0 3

e 9

e APPENDICES n'

e e

6 O

G 0

9 x

jh e'h' 919 h " '* * " ' ' ' ~ ~ * ** *

  • yg 3.5.8

,.'.,Special Project in TLD AN0!!ALY REPodT RESOttf710N FOR}!

>~

StWIARY OF TI.D ANOMALY REPORT:

Refer to interview sheet for sunsnary.

ht.2 4 # 88

.200ATLDr.,n/~r[

Entered APR 2 30643/

u TOLLOt.'2NG STEPS DONE TO RESOLVE :

//Z ) Ys* WJ///y

/'/tsf-

/MSTb y/ 3/zvl/f

/*ob

'rsa swh?

sia if

/tL A fat.l d't '

/*lP#

f 3##l5l I'#Al/

,y/j.'.)/silty A/P

,,2 4 DATE:

FORT! CO?!PLETED EY:

TLD TOE! 003.2 D

w

~

~

~

. r o. ~o..v

, g,,, -

,u-

., ;. g.,

. APPENDIX 3

>~

.s.

e THI ACCIDENT-RADIATION ZXFOSURE YALIDATION INTERVIEW KID REPORT PERIOD OF 28 TERU 31 MULCR 1979 AfebAd 2'Y 0

ME t - IAST. TIRST. MIDDLE IWIT.

SOC. SEC. NO. " EMPLOYER AT TMI IINTERVIEQ DATE Information Fa:k Phone:

,,(home)

Address:_

Sant Date (work) ss 8 *

-f,,,,,,e- ' #,. (q

$ ' * ( '.'

p/

j ft.Q kg

~)

Interviewed by: Phone Date phoned 2/3 I Ccements; m.s.t J sv,e.:1 f,

t//

1/2L p r,- -/...,

4 In person

  • / l~'s d'A'fsq Did you visit the island on the days of Narch 28th thru Harch 31st.19797 o

,, I, A.

- If no - (Stop)

~,

  • /

M Ns 3.

V If ves:

Which dates? 28th i 29th 30th 31st Didyoureceiveaninforzationpackageinform[ngyouthatyouv:uldbecalled concerning your records of exposure?

1.

What was the purpose of your visit to Three Mile Island?

.ks< t (.)fI'E

/

What areas of thep$ b kn: did.-you visg 2.

JOs Mds auf h Afk dreg

~

if$ ks.<

r o

/

/

/

Dates enterad plant: 28th 4 29th 30th 4-31st M Did you wear a radiation monitoring device at all times when you were in 3.

the plant? Yes v-No was it:

a.

Self-reading pocket dosimeter b.

TLD

~

c.

Both s/

Did you wear a radiation =enitsring device at all ti=es outside cf the 4

plant? Yes

.< No Was it:

a.

Self-raading pocket dosine:er b.

TLD r

', ~ -

? l;. - l,;.,-

spptmhx*1

~-

5.

Did you receive notifi:ation of the amount of exposure you received while at TMIT Yes No What was your exposuraf g

What was,'the date range of tha notification?

-r Do you agree with the expo'sure? Yes

_ No If you do n'ot agree with the exposure records or you did not wear s' TLD at 6.

all times inside or outside of the plant:

Identify, from map, areas visited while not wearing a TLD of the island and approximate time spent in each.

area survey exposure level time spent

~

area survey exposure level time spent area survey exposure level time spent o

area survey exposure level time spent area survey exposure level time spent RW7' individual worked on:

Exposure received RWP Date by pocket dosimeter Exposure received RWP Date by pocket dosi=eter Exposure received RWP Date by pocket dosimeter Exposure received M7P Date by pocket. dosimeter g

Exposure received RWP Date by pocket dosimeter Other individuals worked with when not on RWP:

Job Area Job Area Monthly dose received by T1.D prior to March 28th

_ y s t, Monthly dose received by self-reading pocket dosimeter prior to March 28th? ? i 295 Torm 5 dtd TLD MREM Exposure Exposure p'eriod shouir Period be ll/).NlM i:s -l-I41:

.ulm u h1

.i l

l I

y

~~ ~

~~-

  • k..

. : I 'Jd Phun l'l * '. ~.,

y,,,..

Reading not Mrea Data read Assigned on Form 5 Exposure Period

% 7. y

,i 3hDeo 5!-)/

0.

15 y/?-

\\

14d9 stor s.

SAHr-

.yps:3po'~3!

zo to s==ry.

deso.)

$.9 r,1 J rs'trr#'

'.),

..ss>u,e of s m> L t4 c,

J e t%<44,e ' > / u.- s i.h+. c.,. -, s a :r< m Y < a., n,,.bfE:wo

the,

>/

2 Trin L. 4,ct e 1 A.,

o,.. / h A;fe..m,4. /- k

~

3,s' # 1.9 f l kf /W N. b. a. f

  • e. < A b

' h v ~.

.., / < D /

n z.

x,. c ~ w z ll N, '!/

L 1,, ac,,, 'f /ra AN'.' Ar e.'.

5%. s e,

z y

4r t-

.p. >. A:J.,,

/roo 1 da s/r #..., u 7.c i.-

.f.. <

$3f'4.,r./ w.1 b ui< La Aw., <n,i

,,far/Ac z,J N J v.d 6 A-a iA' bL A >- D

~

< f u,/4 s, u f. /* ><>ed S enAe.'

=

d'/ d.,,s d n>i,,*C A n. i.h,, ds;.

g 1

~

e O

i

- - - -, -. - ~ - - - -, - - - - - - -

-n---

,r-~,---,

,a t h 4 -

...s Actico Tcken S

s NRIN dose.de. ducted frein TLD #-

g a

)RDI dose dose assigned to T1.D #

i.

NRDI calculated dose assigned for period All changes verified on Form 5 dtd Signature 7

I:cposure changes notification by: Term ler dtd Sent Letter of reply r

c C.M -

/'lb (&.

$ s I:&e'stigator

~

Reviewing Super 71sor i

t 1

.m

.e m........

a p <-

T M far..:2BRr. Es.itet. recevdeA on jonlt our-ruf I '

Y: ':~j.

s TL 0 t.pu t9 A. ? 1 BOO ha..+ L.sorn ts.'ll. MOD < <<tt.h..

d h

Q--.f k5. 7.f '..

..-l,.

/t

.lh D -.}'

$6 0* ' "g, c...f p,, n.s..

ei 40 I

N6 d4

.- J..lu.-

4

{8-..:M, p....

i

j f'.i u s.

f

, eh att. -)..p(\\ 'Iy...

.--. Q )

...... -. - i -

.. - g '?,

q.

d 4

4 q

%c5 i

.......-......-..-.--.--...-.-4.c.M. f

< 3.s,.

  1. p s

p.0

._......... --.,. n. pp. -

84 -

....J.8

/

t s

-.~

Q.. Y.\\

.I

.... a.:

e

/

-n

,e.

PERSONN[LDOSIMETRY A.

WME

(

B.

HOME ADDRESS (Street)

(City)

(State)

(Zip)

~

M JP N

C.

CD ANY (Name)

(Address)

D.

SOCIAL SECURITY NUMBER

.'. ~

BIRTHDATE /8[/f/CM

' AGE 1h o.

JOB TITLE M n.ic MET-ED EMPLOYEE N'0. 8[A1 E.

4

.....=..............=

a....

Yes

.No F.

Have any of your previous employments involved a radiation exposure?

If yes, please complete section 5, 6'and 7 of the NRC Form 4 on the reverse side.

Have you received any radiation exposure during the present calendar quarter of this G.

year? Yes _ No If yes, approximately how much?

I certify that the exposure history provided by me on this form is correct and H.

complete to the best of my knowledge and belief.

(All Dosimetry must be in the Dosimeter Rack at the end of the month)'

a (Da te)..

(51gnature) 4o If Dosimeter or TLD is lost form must be accompanied by a 1612 form.

H.P. Lab Use Only Neutron Number TLD Rei ssue.................Yes....hu Assigned TLD Number 300 0 3 /

. Release Form s( ) Signed......Yes No Form 4 Signed.......'........Yes N

Technician (Signature)

Urine Bio. Sample Obtaine::...........Yes No JiP Supervisor / Foreman Urine Sample fiumeer.........

.................................................n......~.=...a..=a-a*a Clerk Use Only Receivec_

Date Sent for Records:

Company m

ee I::1,:

-~ - - - - -

l..:

~

aeEuvx 1

3...

~ ~ * ' '

ACTION TAKEN i

W.ETE:

mRam TLD#

Exp2sure Period i

to 1/'J//19 ffs /3

/C D 6 3.T

'Tl/

1.~

j i

j ADD TLD#

mrem Expssure Period i

/cs 0 & ' l C 2ll to 'ih s-l19 lono JosoJ/

ph.

/> rs!91

/t/ o s 3 o n 6 ~3 /

W t.>

7/is/'2;

.e 10 s

w All changes verified in Form 5 dated [ [//

O-Signature M z/

Ixpssure change notification by: Term letter dated Sent

[

Letter of reply Sent By 1

  • - 7/

~

{

/f n

()

'V Reviewing Supervisor 2tivastigator i

i

' S 3...' T ~

APPP.NDIX If..

  • t O

@ssN@&nSF#SMMMEW*MW@iWAM 4-/ 3-/75 5 p/

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n.

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-u? n.:'~i..........

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5"'.i

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AM EKoIX 2 t

.s

' INTERVIEW OF AUX. OPERATOR "T" by CORDON M. LODDE and CHARLES SHEDLEY 1)

On July 24, 1980,' Cordon Lodde and Charles smedley of PCI held an interview with Aux. Operator "T" to determine his acti ties during the period March 28, 1979 to April 2,1979, which may have led to his alleged radiation exposure of about 10 rad beta and 1.4 rem gamma during the period March 28, 1979 to March 29, 1979.

2)

Discussions with Aux. Operator "T" indicated that he had been called into work early on Msrch 28. He arrived at the Unit I Processing Center (PC)

IVH.Segf at or about h on March 28. He was issued a temporary TLD badge, number 300631 and a self-reading pocket dosimeter at Unit I because his normal I

TLD was located at the Unit II HP Control Point. When Aux. Operator "T '

started through Unit I to Unit II he passed close to the Unit II primary sample lines. While in this area, he read about 100 mR on his self-reading pocket dosimeter. He decided to get out of the area, and then proceeded to Unit II by another way.

3)

At about 1700-1800 on March 28 Aux. Operator "I" and Ron Fountain were to I

I

, so to the Unit II Radwaste Disposal Control Panel (RWDCP) on the 305' level

/

of the Unit II Aux. Building to perform a valve line-up and start a pu=p to transfer pre-accident water from Unit II to the Unit I MWST.

(Discussion with Earl Showalter on July 29, 1980 indicated that both Unit II Aux.

Building Neutralizar Tanks (WDLT-8A and WDLT-88) were transferred to Unit I 1

MWST. The transfer of UDLT-8B took piece between 0700 and 1200 on March 29, i

1979).

j 4)

Aux. Operator "T" dressed out in one suit of cetten Anti-C, a wet suit, and l

)

SCBA; however, he did not west a head cover. 'ie is not sure if he vore his street clothes under his Anti-C.

Someone helped hin dress out but he is r.ot

^

. s.kwb; 2. -

u--+

2.
. - J.-J. : ^

sure who it was. He thinks he were his TLD under the wat suit, but is e

s not sure if it was under the cotton coveralis.

astrument which 5)

Aux. Operator "T" had an Darline, Model R0-2, survey z.

)

pegged at greater than 5 R/hr. immediately after he satered the Unit II Aux. Building; however, he continued to the RWDCP to perform the valve line-up and he started the pump transferring water to Unit I.

6)

The distance from the Unit II Aux. Building HP Control Point to the RWDCP is about 240 feet. Aux. Operator "I" stayed at the RWDCP for about five (5) minutes. It took him about one (1) minute to perform the valve line-up and start the pump; however, he had to wait about four (4) minutes for the See enclosure 1 for AIzz.

Unit I Shif t Supervisor to acknowledge his page.

Operator "T"s path from change area at Unit II EP Control to RWDCP.

7)

Either before or during Aux operator "T"s entry 1sto the Unit II Aux.

Building, he said that he was told that the make-up tank had been vented.

(A review of available records indicate that the first time the zake-up tank was vented was at 0435 on March 29, 1979).

Aux. Operator "T" stated that he was not contaminated with radioactive liquid l

8) during his entry; however, when he returned to the Unit II Control Room, he cet off the monitors.

(Most probably he had noble gases trapped in his clothing and hair)

_9)

When Aux. Operator "T" read his 1 R full-scale self-reading pocket dosmieter upon exiting the Aux. Building, it was off-scale. His TLD was read at -2000 e f

March 28, 1979 af ter his going to Unit I to shower. Aux. Operator "I"

stated that no further reduction of body surface contamination was noticed in the readings af ter he showered several times because the backtround Icn radiation levels of noble gas were so high in th'e dressing area that

_ _ _ _ _ _. ~ _ - _

i*

levels of coistamination could not be detected. ' Aux. Operator "T" was re-issued his TLD and performed on-site surveys until be departed TMI at after about 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> on-siteh about 0400 on March 29, 1979

(-

10). Auz. Operator "T" returned to THI at about 2300 on March 30 and departed THI at about 0700 on March 31. During this period he conducted surveys outside the plant and received about 15 aren ganssa exposure.

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19. 1980 INTERVIEW OF AUX OPERAhR'*T" by S. W. PORTER JR.. C.W.P. on Septrabir 1),

Dressed out in Control Building,' hallway outside cabh room.

.J 2)

Someone helped him dreas, however, he is not sure wbsit us.s, may have been Plastics (top and botten) plus street clotbas '(T shirt and

[

Hike Janovski.

Head Pants) plus heavy orange gloves plus black booties and Scott air pack.

Most bare, hair contaminated, approximately 10,000 eps afssr three washes.

i-Test and wrists taped.

sone af ter approximate'y 4 or 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

3)

Entered Aux. Building with Roc Tounta,in. Inside Aux. Building approximately 3 minutes, mostly at Radvaste Control Panel. ThinksTLD was clipped to pants pocket, not really sure.

o Ron Fountain spent much more time l'n Aux. Building, at the same time as Aux.

4)

Operator "T".

Window Survey meter off-scale at 5' R/hr. as he entered the Aux. Building.

5) opent? Not sure, but probably closed. 'High range (1 F} pocket dosimeterJ off-scale.

6)

Did not go downstairs.

7)

Time of entry? Between 1800 and 1900.

8)

No RWP to sign-in on.

9)

Entry authorized by Joe Chwastyk.

Unit I HP Office - approximately 10 minstes waiting for. respirator e

~10) a)T=0 l

Observation Center issued TLD.

Went back to Unit I service Building to get Ron Tountain, gave hic b) T = 5 respirator.

Went back to Unit I HP area to Unit I Anz. Buildir.g (under sarple lines approximately 10 to 15 feet away, approximately I to 1.5 c) T = 5 minutes),

Vent back through Unit I HP to Unit II Centrol Roes.

d) T = 5

~

f

./.g In Unit 11 Contral Room fer awhila pri r to 331ng to Turbina e)T=7 Building.

In Unit II Turbine Buildiss approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> working on f) T = 120 vacuta pumps.

'Ihen went into Unit II Aux. Building at appr6ximately 1800.

g)T=5

~

Want to showers in Unit I and in Wash Machina Room washed h) T = 45 clothing.

  • T is in minutes Vent TLD was set-up in a trailer near where RAD Services is now located.

11)

Told there at about 2200 to have TLD read, af ter shower,1.4R reading.

Did not recognize the individual who read approximately 4 to 5R beta.

his TLD.

d Went to see Tom Mulleavy in Unit I Control Room at approximately 2000 or 12) 2100. Mulleavy sent him home immediately.

Back of neck, skin prob, ably bare above plastic top because neck was not 13) taped and he did not wear a hood (if no coveralls were worn).

Not_ sure - he may have worn coveralls which would

14) Did he wear coveralls?

If he wore coveralls, the TLD would have been

/

have covered ba,ck of neck.

clipped to outside of coveralls and inside wet suit top.

(and coveralls 7) in Unit II Circulating Water Pump House??

15) Found wet suit
16) Almost sure that vet suit was over TLD so that he would not loos 6

O

~~'

a.1.. ::@".~

2...

' inE IROPOiii AN ED15ON C O M I' '. N Y

s. mi,. e.
.~..

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s.

Location TLD Buildf rir Subject IX)ST. CVALUATIO:1 TOR T!reti:!CL TI.1..

IN STORAGE RACKS DURII:G TI'T. ACCIDEIIT 088 -'

July 19,3972 To Tile (Report No. 1)

A.

BACT.GROUl!D INFOR!!ATIGQ At the time of the acci. lent at Three Hile Island Iluclear Staties.

1.

(THIllS) on March 89,1979, Personnel Thermoluminescent Dosimeter:-

(TLDs) which were previeusly issued to Statien and contractor personnel, were snMacted to various amounts of radiation exposure while :rered in badge racks.

Control.TLDs, which norna11y indicate background radiation 2.

o The levels, were re.1 for cach of the TLD racks in rpiestion.

control TLD located in Unit I badge rack indicated 0.8480 renn m.'s-the control TLD located in Unit II badge rack Indicated 1.0B0 r.r Security personnel TLDs stored in the Processinr Center, wers.

determined to inelicate an average reading of 0.100 rems hight:-

than normal.

Security Personnel do not routinely enter or occupy restrictad areas and subsequently recalve minimal

~

exposure durins: nortimi assignments.

Based on contre 1 '11.D vt.adini;s located in Unit:. I and II b..dge l

3.

racks and additional e:-:posure received by Security Personnel TLP.

stored in the Procar. sine. Center, adjustmentr. vere made to eacl.

individual's TI.D r..adinr. subtracting expenmv 1:;11eved not te have been receive.1 1.y the individual.

TT.El.l*:f:'*ii'? - 00:1::E!!TS C *:.Y v.,

...m. neries rut.innaffntti.1

.01;.013 v.

-.,s g

,e 4

Based on the l'n(t 1 c.catr-3 TLD reading of 0.480 rems and th..

physical locarian ef the TLDs, 0.300 rems west sul.tracted frer.

TLD identification numbers from 300000 to 30025n and 0.400 rem.

were subtracted from TLD identification nurobers ID0250 to 30051.

Subtractions wara in3y made from the group which were read pur

~

on the =ame day, isrued during the period frra 3/1/79 to 3/27/73, and were found to be equal to or in excess of the values above.

The values chosen to be subtracted were essentially the lowest value in the group.

Based on the Unit II control TLD reading of 1.000 rems gamsa a::d 5.

7.300 rads beta an adjustment was.made to all TLDs whose expori::

a

/

equalled or excend<.d these values.

Based on the avarnce randings of Security Per;ennel TLDs locotr '

6.

the Processing Center an adjustment of 0.100 rtra was applied t-allTLDswhoseexpenureequalledore.Eceededthesevalues.

B.

DOSE EVALUATIO:1 1.

The readout for tha control TLD located in Unit I cannot b,e located for beta'evnluation..

2.

The two control 1.ndt.es were not calibrated at the time.the exposure reductions uere formulated to substantiate that their response met the enlil r ation criteria require d by Station Proced :: r,.

3.

Interview: were hald with selected individual:. less than 10 cf 1: 1 thos.- af fected, an 1 in lientionn from the:e paa;ile substantin'.-

1 the fact thz,r th y tre e < not on r.ite durin;. the accident.

PIT.!1:'I::!FY - CO:-;iE! TS 0::LY

e e

e e

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. J': rte Conouttants, Inc.

APPENDIX 5

  • 73 oITTENee2U$t PLAct e

AR oamo n t, P A.19003 e

assa w sass Scytember 16, 1980 j.

^

~

70:

Sydney W. Porter, Jr.

TROM:

Mike Buring

SUBJECT:

Alleged Beta Overexposure The following are my observations after spending thae day at 1MI talking with various people concerning the alleged overexposure.

1)

TLD System was operating properly.

s 2)

TLD card was operating properly.

3) operator of TLD System is unknown.

4)

Need R. Beldon's records of beta / gamma TLD response for zunon in Aux. Building, or other.

5)

No self-reading dosimeter records available.

6)

Records of Unit II area badges not available. Check with Terguson, Bob L.,

Ira Seybold.

Should have been 100's R.

7)

Camma number good on TLD badge.

8)

Beta number on printout cannot be discounted.

9)

Other personnel entering area did not receive similiar beta exposure.

10) Beta correction factor of 4 any possibly be adjusted by 4) or 6). Call Bob Laviemonier and Tom Peterson of Electric Boat on beta.
11) Contact people should be Reppert (GPU), Hilford (GPU), and Seybold (NSS).

~

7xU

.d%L

/(fike Buring

\\.

MB/sa

.

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