ML19256G461
| ML19256G461 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/05/1979 |
| From: | Wilson R METROPOLITAN EDISON CO. |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| GQL-1499, NUDOCS 7912310337 | |
| Download: ML19256G461 (60) | |
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Metropolitan Edison Company y
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Post Office Box 480 gl e p*f f
('A Middletown, Pennsylvania 17057 717 944-4041 Writer's Direct Dial Number Dece=ber 5,1979 GQL lh99 Mr. 3. E. Grier, Director Office of Inspection & Enforce =ent Region 1 U. S. Nuclear Regulatory Cc==ission 631 Park Avenue King of Prussia, Pennsylvania 19h06
Dear Sir:
'I"nree Mile Island Nuclear Station, Unit 2 (DII-2)
License No. DPR-73 Docket No. 50-320 August 28, 1979 - Persennel Radiation Exposure Enclosed is the updated Dose Assessment frc= the August 28, 1979 entry into the DII-2 Fuel Handling Building North Make-Up Valve Roc = to examine and tighten the leaking make-up valves. The assessment contains the final results of our investigation into the personnel expcsures which occurred on August 28, 1979 and is submitted as stated in our letter (GQL 1188 ) of Septe=ber 28, 1979 Since this incident also reflects a violation of 10 CFR 20, a Licensee Event Report (LER) vill be included in the next Quarterly Report due on January 15, 1980.
A persennel code identification sheet is enclosed on a separate page.
As indicated in the Septe=ber 28 letter, the corrective action to prevent a recurrence of this event has been taken.
This involves detailed reviews by Radiological Engineering personnel and Sadiological Control Supervision for any job involving access to highly conta=inated areas with beta radiation fields in excess of 2 R/hr on an instru=ent with the "vindov" in the open position.
Such entries vill involve the use of extra protective clothing and desi=etry to properly protect and conitor the workers beyond what vould otherwise be required. The protective clothing, dosimetry and instrumentation which is available to improve radiological centrols in these environments is being further evaluated to improve our ability to safely verk in these conditions.
Submittal of a schedule of activities in this investigation as requested by your letter dated Nove=ber 13, 1979 vill not be submitted inasmuch as this exposure assess =ent is complete.
V
~ ncere y, 1665 001 6
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1 RW:LWE:tas R, F. Wilson 7g1g310 37 Director - SII-2 Enclosure MetreacMan Ecson Comcany is a t.'emter of the Gene'ai Pue:ic Ut ' t es System s
E*.
B. H. Grier, Director December
, 1979 GQL lh99 cc: Office of Inspection and Enforcement Division of Reactor Operations Inspection U. S. Nuclear Regulatory Consission
'4ashington, D.C.
20555 1665 002
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IDENTIFICATION OF PERSONNEL CODES OF UNIT II WORKERS PAGE BIANK - NOT FOR PUBLIC DISCLOSURE (CONTAINS 2.790 INFO) 1665 003
November 30, 1979 DOSE ASSESSMENT FROM THE AUGUST 28, 1979 ENTRY INTO THE TMI UNIT II FUEL HANDLING BUILDING NORTH MAIC-UP VALVE ROOM TABLE OF CONTENTS Abstract Page 1 Su= mary of Overexposures Page 2 Introduction Page 3 Available Data Page 3 Preliminary Technical Considerations Page 4 Evaluation of The Ga=ma Dose Page 5 Beta Dose Estimation Page 5 Estimation of Statistical Uncertainty Page 7 Discussion and Conclusions Page 8 Tables Page 11 Figures Page 16 Appendices Page 28
-A-1665 00u4
November 30, 1979 i
LIST OF TABLES 1-Early Reported Readings (9/29/79) and Staytimes In Page 11 The Valve Room for Each of the Individuals Involved on 9/28/79 2-Radioisotopic Composition of the Primary Coolant on Page 12 September 10, 1979 and the Associated Beta Yields, Energies and Ranges 3-Dose Indications on Self-Reading Dosimeters Worn By Page 13 Individuals Entering The North Bhke-Up Valve Room 4-Dosen to Unit II Workers From Make-Up Valve Room Page 14 Fields 5-Locations of the TLDs Used to Esti= ate Doses to Page 15 Organs Not Covered by a Dosimeter 1665 005
-B-
November 30, 1979 LIST OF FIGURES 1-Protective Clothing Worn by Individuals Entering the Page 16 Make-Up Valve Room 2-Material Thicknesses Over the Body and Material Page 18 2
Thicknesses Under TLDs, mg/cm 3-Thicknesses of Protective Clothing in eg/cm Worn in Page 25 Different Combinations by Individuals Entering the Make-Up Valve Room 4-Net Beta Response of Harshaw TLD 700 Chip as a Function Page 26 of Absorber Thickness 5-Sensitivity Index for the TLD 700 Chip Page 27 1665 006
-C-
November 30, 1979 DOSE ASSESSMENT FROM THE AUG. 28, 1979 ENTRY INTO THE TMI UNIT II IUEL HANDLING BLDG. NORTH MAKE-UP VALVE ROOM ABSTRACT AND StifARY TABLE This report describes the work performed to assess the doses received by the six persons who entered the Three Mile Island Nuclear Generating Station Unit II North Make-Up valve room on August 28, 1979 to repair leaks in the packings of some of the valves in the room. All of them wore multiple personnel conitors ( TLD badges and self-reading dosimeters in various combinations and distributions over the body).
The TLD badges worn by the workers indicated far higher beta readings than had been expected on the basis of the gamma survey performed with a "Teletector" survey instrument prior to commencement of the repair work. This procedure has been changed to require beta surveys prior to all Unit II radiation work in areas where any appreciable beta fields may be expected to exist.
The reportable overexposures,as per 10 CFR Part 20, resulting from the valve room entry are presentad below. As indicated, there were two reportable cases of extremity overexpcsures and six reportable cases of skin of the whole body overexposures. All of the overexposures were due to nonpenetrating, or beta, radiation, and are therefore to be considered as overexposures to the skin.
In order to perform the dose assessments, extensive studies, both theoretical and experimental, were perfor=ed to evaluate the response of the TLD badges to mixed beta fields from the primary coolant. Some of the results of this work are presented in this report, but additional details will be presented in a separate technical report dealing with the problem of personnel monitoring for beta exposures using TLD badges. Comprehensive interviews, detailed mock-ups, and TLD irradiations in the Make-Up valve room were also undertaken in an effort to obtain information on the field distribution in the valve room, and also to obtain details on the clothing and personnel monitoring equipment worn by the workers during the valve room entry.
Our standard primary coolant beta source was calibrated by NBS.
The table below gives a summary of the overexposures. The doses are to be considered as skin doses. The units are in rads.
1665 007 Page 1
Summary of Radiacion Overexposures Recieved by TMI Workers During the August 28, 1979 Entry into the Unit II Fuel llandling Building North Hake-Up Valve Room WORKER Organ Dose (rads)
Dose (rada)
Total For Overexposed August 28, 1979 Rest Third Quarter, 1979 Third Quarter (rada)
Beta Ganuna Beta Gamma Beta Plus Gamma II.P. Foreman A Skin (both legs) 39 0.6 0.3 0.35 40 Aux. Operator C Skin (left leg )
25 1.0 0.0 0.2 26 Aux. Operator D Skin (left leg )
12 0.8 0.0 0.4 13 Aux. Operator E Skin (right leg) 28 0.8 0.0 0.03 29 Aux. Operator I Skin (right leg) 165 0.8 0.0 0.26 166 Skin (left hand) 81 0.8 0.0 0.26 82 Aux. Operator J Skin (right leg) 160 0.5 0.0 0.3 161 Skin (left hand) 37 0.5 0.0 0.3 38 Nate :
Doses to the skin of the legs are considered doses to the skin of the whole body and are therefore subject to the quarterly limit of 7.5 rada. Poses to the hands are considered to be extremity doses and are therefore subject to the quarterly limit of 18.75 rada.
Ln The relative etandard deviations on the total doses are 15%.
C o
Page 2 CD
DOSE ASSESSMENT FROM THE AUGUST 28, 1979 ENTRY INTO THE TMI UNIT II FUEL HANDLING BUILDING NORTH MAKE-UP VALVE ROOM A. - INTRODUCTION On August 28, 1979, six persons made individual entries into the North Make-Up Valve Room to evaluate and repair leaks from some of the valve gaskets.
Preliminary surveys, using a survey meter, indicated a gamma field of 10-15 R/hr. in the room and around the piping and valves. All individuals involved,
except the H.P. Foreman, wore multiple TLDs and/or one or more self-reading dosimeters.
The H.P. Foreman wore one TLD and two self-reading dosimeters.
The TLDs were subsequently read out and some of them indicated doses received that appeared to be above the allowable limits, particularly the beta doses, or as it is sometimes referred to, doses due to non-penetrating radiation.
Based on these high readings, a dose assessment study was initiated to determine the extent of overexposure, if any, to each individual.
B. - AVAILABLF DATA The data on which the dose assessment was based is presented in the Tables attached. Table (1) shows the initially reported ILD readings for each of the individuals, together with the staytimes in the valve room. The protective clothing wern by each individual is shown in Figure (1), and the total thickness of clothing is summarized in Figure (2).
In this figure the clothing thickness over each part of the body is shown on the lef t hand diagram in units 2
of mg/cm. The right hand diagram shows the thickness of clothing that was 2
worn under each TLD in units of mg/cm, wherr applicable. The clothing thicknesses used tc calculate these numbers are shown in Figure (3).
Su=maries of interviews conducted with each individual are given in the Appendix. These interviews were conducted in order to determine and supplement O
1665 009 Page 3
information on number and types of clothing worn, number of TLDs and self-readers used, clothing under the TLDs, and type and location of work performed. Also given in the Appendix are copies of the calibration certificates for the "Teletector" survey instrument used in making the surveys in the valve room. One of the calibrations shown was performed 36 days before the August 28, 1979 valve room entry. and the other was performed 14 days after the entry.* The normal calibration interval for this type of instrument is three months. A floor plan and elevation view of the Make-Up Valve Room is included with the interviews to assist in visualizing the events described.
O. - PRELIMINARY TECHNICAL CONSIDERATIONS The TLD badges worn by the individuals into the Make-Up Valve Room are the standard two-chip Harshaw badges.
The two chips are sealed between two teflon sheets and mounted on a TLD card which fits into the badge.
Each 2
of the teflon sheets is 16 mg/cm thick.
The chips are extruded lithium 2
fluoride of a thickness of 0.035 inch.
Based on a density of 2.64 mg/cm 2
for LiF, the chip thickness is 234 mg/cm.
The card utilized two Harshaw 700 chips.
When placed in the badge, the TLD card positions one chip, which shall be referred to as the beta chip, behind an open window (or collimator). The opening is covered on the outside of the badge by a paper name plate about 2
2 16 mg/cm thick making the total material covering the beta chip 32 mg/cm.
The second chip, which shall be referred to as the gamma chip, is positioned 2
behind an aluminum filter of 230 mg/cm nominal thickness. Adding the thickness 2
of the paper name plate brings the total up to about 245 mg/cm,
Examination of the TLD readings and of the radioisotopic analysis of the primary coolant indicated that the beta fields from the coolant contained components sufficiently energetic to penetrate the gamma chip filter and contribute to the reading of that chip. Table (2) shows the results of an analysis of the primary coolant performed on September 10, 1979 by Babcock and Wilcox.
The sample was representative since it was taken on August 29, 1979. Also shown are the yields, endpoint energies, and maximum ranges of the beta emissions.
Suggestions wera put forward that the two TLD chips in the badge should be referred to as chips recording penetrating and non-penetrating radiation rather than gacma and beta radiation respectively. Although there is some merit in this usage, it was felt that the distinction based on type of radiation rather than penetrating ability is more fundamental, especially since the two types of radiation are attenuated by different mechanisms and, therefore, follow different attenuation laws.
Of course, a borderline area is encountered at very low photon energies where it becomes difficult to separate the photon and beta radiations.
However, at such low photon energies it is usually not important to separate the effects of the two types of radiation, and the purposes of radiation protection and dose assessment are probably adequately served by treating very low energy photons as betas of the same energy and treating the higher energy photons as ga==a rays.
It was decided that attempting to correct the gam =a chip readings for beta penetration through the filter would be very difficult and tha results
- See comments and qualifications in Appendix III.
1665 010 Page 4
would contain too much uncertainty to be of use in dose assessment.
The gamma chip readings were therefore not used in this study. Ga=ma dose estimation is described in the next section, followed by a discussion of beta dose estimation.
D. - EVALUATION OF THE GAMMA DOSES As mentioned in the last section, the TLD gamma chip readings were not used in ga=ma dose assessment because of probable interference from beta rays penetrating the filter in front of the chip. The gamma dose rates obtained from the TLD readings were not consistent and showed large variations by as much as a factor of 16 for the chest TLDs.
Of course, such variations could have been due to a non-uniform field in the room, but other data to be presented shortly does not support this possibility. Also, an experiment performed using the primary coolant as a source showed that at an absorber 2
thickness of'245 mg/cm the response of the TLD corrected for ga==a contribution drops by less than 90% compared to the unshielded response. The large variations in gamma dose rate could be explained by assuming varying degrees of beta penetration depending upon the orientation of the badge with respect to the source.
An angular orientation increases the effective shield thickaess and reduces beta penetration.
The gamma dose estimates are based on the survey performed prior to commencement of work in the Make-Up Valve Room. The survey was performed using a "Teletector" survey meter (calibration certificates presented in the Appendix).
This survey indicated a uniform gamma field of 10 R/hr. throughout most of the room, rising to 15 R/hr. close to the floor and to the leaking MU-V-155.
A hot spot of 25 R/hr. was found at one point on the floor.
Supporting evidence for these field values were obtained from the self-reading dosimeters worn by the individuals who entered the Make-Up Valve Room. Table (3) gives the readings of these dosimeters, the staytimes, and the exposure rates based on the readings and staytimes.
It should be noted at this point that the self-readers probably respond to beta fields to some extent because the chamber walls are not thick 2
enough to stop the higher energy betas (thickness of about 350 to 400 mg/cm ).
Therefore, the exposure rates shown in Table (3) probably contain some beta contributions.
On the other hand, the staytimes include walking from the point of entry to the work area and back. The vicinity around the point of entry is a low field area and the walk back to the point of entry involves some shielding of the self-readers by the body, which, in this configuration is between the source (pipes and valves) and the dosimeter.
These effects are comparatively small, however, since the total entrance and exit times are estimated to make up about 7% of the total staytime.
The above considerations and data indicate that the use of 10 R/hr. for the
.c gamma field above about waist level and 15 R/hr. below that level is probably a good estimate of the existing field, if not a conservative one.
The gamma dose to each individual is based on these values together with the estimated staytimes.
E. - BETA DOSE ESTIMATION Af ter correcting the beta chip reading for gamma contribution, as calculated above, the dose obtained is equal to the average beta dose over the thickness of the c. hip.
Since it is necessary to obtain the entrance dose rather than the average Page 5 1665 011
dose, a factor is used to multiply this average to convert it to an entrance dose.
In view of the fact that the sot ce of beta radiation in the Make-Up Valve Room is made up of a mixture of beta smitters, the conversion factor, which will be referred to as the beta Sensitiv1.y Index, SI, will depend on the relative concentration of the beta emitters. The index will therefore be time dependent because the beta emitters have widely differing half-lives. Also, since the beta endpoint energies are quite different for the 'different emitters, it would be expected that the characteristics of the composite beta spectrum would change with depth of penetraticn into an absorber. This results in the Sensitivity Index being a function of depth at which the dose is evaluated. (Reference Fig. 5)
It was mentioned in a previous section that the TLD badges used during the entry into the Make-Up Valve Room were worn under a variety of protective clothing thick" s, and in some cases there was also some clothing worn under the badge.
This m
.2.
that different badges would require different sensitivity indicies to estimate the beta entrance dose to the skin.
In view of the fact that the necessary experimental equipment was not available to make measurements to determine the required index values, it was decided to calculate them. The Lovinger equation for a thin infinite planar source was chosen for evaluating the depth dose. The Sensitivity Index is defined as,
(*
=
D where D(e) = entrance dose
/
D(x)dx 3=
3 0 x = x2 - x1 D(x) is the depth dose function given by the Lovinger equation. x1 and x2 represent the entrance and exit coordinates of the TLD chip with respect to x, the coordinate 2
for the entrance dose.
Since the chip is covered by a total of 32 mg/cm of material the limits of integration would be, xi = x + 25 x2 = xi + 234 2
The 25 number in the first equation is 32 minus 7 mg/cm representing the skin epidermis. Thus, if the TLD is not covered by any protective clothing, the 2
Sensitivity Index for 7 mg/cm thickness is used.
32 is the thickness of =aterial covering the beta chip.
In order to determine the extent of the validity of this method, an experiment was performed in which the response of the TLD chip was measured as a function of absorber thickness. Aluminum absorbers were used and the source was made by depositing a matrix of primary coolant drops onto a steel plate about 5" x 7" in size. The TLD card was irradiated outside the badge and was held in place 6" above the source by a suitable jig which was designed to also hold 1665 012
the absorbers. The dose rate at the chip location was measured at about 1500 mrad /hr. at the time the source was made.
The results of the experiment are shown in Figure (4) together with a plot of the calculated mean dose at various depths.
It is evident from the figure that the agreement is quite good.
It was also possible to measure one valus of the Sensitivity Index. A TLD reading was'made with no absorber and the dose rate at the TLD position was measured using an extrapolation chamber.
This latter measurement gives an entrance dose rate and when divided by the TLD rate, the result is the Sensitivity Index.
The index was calculated for the same conditions as those in the measurement.
The measured value was 3.6 and the calculated value 4.5.
The standard deviation of the measured value is estimated to be between 15-20%
and hence the difference between the calculated and measuced values is not significant at the 90% confidence level.
Curves showing the variation of SI with absorber thickness are shown in Figure (5) for Sr-89, Y-90, and the coolant mix corrected in composition to the day of the Make-Up Valve Room entry.
Based on the above results, the procedure used for beta dose calculation was the following.
For each TLD, the reading was attenuated to allow for clothing worn between the TLD and the skin using the curve in Figure (4).
The Sensitivity Index was next determined using the curve for the cc int shown in Figur2 (5), at the point corresponding to the total clothing thicknees worn at the TLD site.
Finally, the dose is obtained by multiplying the TLD reading by the Sensitivity Index. This was repeated for all the TLDs worn into the Make-Up Valve Room.
The results of this procedure are shown in Table (4) which gives the estimated gamma and beta doses to each of the individuals who entered the Make-Up Valva Room on August 26, 1979.
Since only a limited number of dosimeters were worn by any individual, some doses, at locations not covered by dosimeters, had to be estimated. The bases for these estimates in each case are given in Table (5). Appropriate adjustments were made in each esse for differences in clothing over and under the TLDs.
It should be noted in this connection that the choice of the most appropriate TLD to use for estimating the dose to an organ not covered by a TLD was aided by a series or re-enactments of the work done 'a the Make-Up Valve Room. These were done by the operators themselves using a sock-up of the room and piping. ?hotographs illustrating this phase of the analysis are presented in the Appendix.
2 In the case of the gonadal doces, a tissue thickness of 300 mg/cm was used between the surface of the gonad and the seminiferous tubes (as per medical consultant's letter to that effect in the Appendix).
The gonadal dose was obtained by averaging the dose from that depth into the gonad up to the maxinum beta range in the gonad.
E. - ESTI1*ATION OF STATISTICAL UNCERTAIh"rY The ga=ma doses were obtained on the basis of "Teletector" surveys.
Since the instrument was certified to have been in proper calibration befors and af ter
- the August 28, 1979 entry, the systematic errors in the readings are relatively small. The random errors ar' estimated to be less than 10%.
- See comments and qua_lfications in Appendix III 16()5 013 Page 7
1 Experimental measurementa on a series of TLDs showed that, in the lowet beta dose ranges shown on the badges worn into the Make-Up Valve Room, the random errors in the chip readings are on the order of 4-5%; therefore, 5% is used for the relative standard deviation of the beta chip reading.
The beta dose is calculated using the formu'la, D=(B-G)AxF
- where, D = beta dose B = reading of TLD chip (open chip)
G = gamma dose as calculated in section E A = attenuation factor to allcw for protective clothing F = beta sensitivity index An uncertainty of 10% is assigned to A and 10% to F. These numbers are based on preliminary sensitivity studies of the two factors.
Based on the above considerations, the uncertainty in the beta dose is estimated to be 15%.
G. DISCUSSION and CONCLUSIONS
- 1. Basic Assumptions : the basic assumptions used in arriving at the doses to the workers considered in this report were that the survey performed on initial entry using a survey meter adequately mapped the gamma field, that the beta TLD chip registered a quantity that is proportional to the skin entrance dose, and that the beta field energy spectrum in the Make-Up Valve Room is closely represen-ted by the field from the isotope mix found in the sample of primary coolant on August 29, 1979, one day after entry into the valve room.
The first assumption appears to be adequately confirmed by the self-reading dosimeters worn by the workers, and is probably also on the censervative side. The self-readers did not, in any case, show a gamma field greater than 15 R/hr. In two cases, however, the dosimeters appeared to have reached their maximum dose reading which in these two cases give dose rates of 15 R/hr. and 10 R/hr. Unfortunately these two cases involved self-readers attached to the wrists and the closest TLD chips were beta ring badges; therefore no gamma chip reading is available close to the self-readers.
The closest ga=ma chips in both cases were in the chest badges. In the apparently worse of the two cases mentioned above, the chest TLD gave 1.05 rads gam =a and 52.37 beta. Based on the attenuation curve shown in figure (4), the beta dose after passage through the gamma filter is about 12% of the unfiltered beta dose. Applying this factor to the beta chip readings and then subtracting from the gamma reading gives a ga=ma dose rate of about 18 R/hr. Thus the dose rate actually used, namely 15 R/hr., is not much in error if the 18 R/hr figure is accepted as exact, which it should not be since the correction for beta interference is only approxi= ate.
1665 014 Page 8
The assumption that the beta chip gives a r eading proporticnal to the entrance dose to the skin and that the proportionali:y factor is obtainable analytically or experimentally is salid only if it is assumed that the colliestion provided by the TLD badge does not materially aff ect the chip reading or, if it does, it affects it in a constant and predictable way. This is probably never entirely truc, but it is a fairly good approximation for a diffuse field (i.e. not a directional beam). Based on experi= ental irradiations in the Make-Up Valve Room, the field does appear to have been diffuse, and on this basis no corrections were made for possible badge collimation effects. It must, nevertheless,be pointed out that some small effect is inevitable and that the effect is in the direction of underestimating the dose received.
The assumption that the beta energy spectru= from the coolan is si=ilar to that existing in' the Make-Up Valve Room forms the basis of the calculation of the beta sensitivity index, the factor used to convert the be:a chip reading to skin entrance dose. Survey TLD exposures in the Make-Up Valve Room, after the August 28, 1979 entry,did not yield any conclusive infer =ation on the energy spectrum of the beta field,and relatively more sophisticted =easurements were needed to map the energy distribution of the field. However, i: was decided that the benefits to be gained from such an affort did not justify the risk of additional personnel overexposures. Also, even if such.easurements were made it would still have been necessary to assume tha: the rield aad not c hanged af ter completion of the repair work. This may not have been a valid cssumption because the repairs stopped the leaking of primary ecolant into the roca.
Preliminary calculations also indicated that the bremsstrahlung fields that may have been generated by the beta emitters probably did not make a significant contribution to the doses received. In view of these considerations, the assumption made above regarding the beta energy distribution appeared to be the most reasonable.
- 2. Future Personnel Monitoring : based on the experience gained fre
- he Make-Up Valve Room entry and the subsequent dose assessment studies, important changes are planned in the area of personnel monitoring and radiation field surveys.
It became evident from the studies made in connection with the dose assessment that survey instruments are not handled with the care necessary in utilizing measuring instruments of this kind. The limitations of the instruments in terms of their ability to measure radiation tields of diff erent qualities also do not appear to be widely understood and the response curves are not readily available for inspection by the users. This is especially true in the case of beta surveys which, under the best of conditions, are difficult undertakings to perform and correctly interpret. Educational programs are needed as well as stricter accountability for the proper upkeep of survey instruments.
A search has been initiated for beta survey instruments with a sufficiently high dose rate range to permit surveys prior to any work in potentially high radiation areas. Preliminary findings indi: ate that very few commercially available instruments have a high enough range for the recuired application. Serious problems are anticipated in the calibra: ion and respcase 1665 015 Page 9
The reason is that there are few characterization of any instrumen. a ci -+
well calibrated high intensity be a
- available covering the required energy range.
The study also indicated t iat PS-eecoonse of the TLD badge to the fields from the primary coolant from o
'.I is not adequately understood and quantified. Therefore, further exper~.
.1 and theoretical work is underway to correct this situation and v s-design the TLD badge to a form more suitable for use in mixed ga==a/high-energy beta fields.
- 3. Further Reports : it is anticipated that the technical findings resulting from implementation of the above recommendations will be presented in further reports.
1665 016 Page 10
TABLE (1)
Early Reported TLD Readings (9/29/79) and Staytimes In The Valve Room For Each Of The Individuals Involved on 9/28/79 WORKER DOSES REGISTERED BY TLDs, RADS Left lland htightlland Chest Left Knee Right Knee Left Foot Right Foot Staytimes, Min.
A 0.55 y 2.5 15.89 e C
3.1 8 8.4 8 0.27 y 1.74 y 0.8 y 3.8 3.4 6
38.6 6 7.2 g
D 7.06 2.4 8 0.42 y 1.36 y 0.79 y 3.0 1.72 8 10.58 8 7.51 6 E
2.0 6 0.856 0.26 y 0.41 y 0.59 y 3.25 8.58 6 5.02 6 8.59 8 I
40 8 27 6 1.05 y 4.47 y 6.69 y 3.0 52.37 8 119 g
149 g Os Os W
J 18 6 3 6 0.43 y 3
y 6,16 y 2,0 e
e 4.92 g 67.28 6 143.66 6 C
N Page,
TABLE (2)
Radioisotopic Composition of the Primary Coolant On September 10, 1979 and the Associated Beta Yicida, Energies, and Ranges ISOTOPE ACTIVITY BETA ENDPOINT YIELD HAXIMUM RANGE 2
pC1/ml MeV*
mg/cm Sr-89
~171 1.463 100 660*
Sr-90 27 0.546 100 185 Y-90 27 2.284 100 1100*
Cs-134 15 0.662 71 240 0.410 1
125 0.089 28 10 Cs-137 73 1.176 6
505*
0.514 94 170 140 0.15 1.020 62 420 0.830 4
325 0.590 10 205 0.460 24 145 La-140 0.15 2.164 8
1030*
1.680 18 775*
1.365 46 605*
1.150 19 490*
W 0.857 4
340 CD 0.510 5
170 CO
- Maximum range exceeds gamma chip filter thickness Page TABl.E (3)
Dose Indications on Self-Reading Dosimeters Worn By Individuals Entering the North Make-UP Valve Room INDIVIDUAI.
POSITION OF READING STAYTIME EXPOSURE RATE CODE DOSIMETER mR Minutes R/hr A
Chest 265 2.5 6.4 Wrist 300 2.5 7.2 C
Chest 150 3.8 4.0 Wrist 350 3.8 5.5 D
Chest 180 3.0 3.6 Wrist 425 3.0 8.5 E
Chest 175 3.25 3.2 Wrist 350 3.25 6.5 I
Chest 650 3.0 13 Wrist
>500 3.0
>10 m
J Chest 410 2.0 12.3 Wrist
>500 2.0
>l5 c
Page
~~
~
TABLE (4)
DOSES TO UNIT II WORKERS FROM MAKE-UP VALVE ROOM FIELDS WORKER H.P.
Aux.
Aux.
Aux.
Aux.
Aux.
Foreman Operator Operator Operator Operator Operator A
C D
E I
J Left Hand y
0.6 0.6 0.5 0.5 0.8 0.5 6
7 6.7 12 5
81 37 Right Hand y
0.6 0.6 0.5 0.5 0.8 0.5 S
7 15 4.1 2.1 55 6.1 Chest y
0.6 0.6 0.5 0.5 0.8 0.5 S
12 2.5 1.2 6.4 51 32 Eyes y
0.6 0.6 0.5 0.5 0.8 0.5 S
0 0
0 0
0.1 0.1 0.6 1.0 0.8 0.8 0.8 0.5 v
Left Le3 39 25 12 3.2 128 74 Right Leg y
0.6 1.0 0.8 0.8 0.8 0.5 A
lo a
7 1 79 169 160 Left Foot Y
0.6 1.0 0.8 0.8 0.8 0.5 8
3.6 5.1 1.5 0.4 13 7.4 Right Foot y
0.6 1.0 0.8 0.8 0.8 0.5 8
3.6 0.8 0.8 3.3 16 16 Gonads y
0.6 1.0 0.8 0.8 0.8 0.5 S
0.4 0.3 0.1 0.3 1.5 1,4 Doses in Rads Beta doses are_ skin doses except for Gonad & Eye Beta dose.
- Beta dose is dose co skin of enkles since all operators wore street shoes in addition to protective clothing.
1665 020 Page 14
I 1ABLE (5)
Locations of TLDs Used to Estimate Doses To Organs Not Covered By a Dosimeter Location of TLD On Which Dose Is based ORGAN A
C D
E I
J Eye Chest Chest Chest Chest Chest Chest (I) -(1)
Conada Knee Knee Knee Knee Knee Knee Left Foot Knee L. Knee L. Knee Right Foot L. Foot R. Knee R. Knee Left Leg Average L.-Foot L. Foot L. Foot L. Knee (I)6(J)
Right Leg L. Leg R. Foot R. Foot R. Foot Lef t 11and Chest Right lland L. Iland LT1 C
(1) The chest TLD of Operator (I) was used because there are some indications that the che'ht TLD of N
Operator (J) was shielded by his respirator.
Page.
I i
j FIGURE (1)
Protective Clothing Worn by Individuals Entering the Make-Up Valve Room
__H.P. For eman A Head:
SCBA, stocking cap, cloth hood Hands:
1 pair cotton gloves, 1 pair surgical gloves Whole Body:
1 pair shorts,'l pair cotton coveralls, 1 pair paper coveralls Feet &
Ankles:
6 pair plastic boots, 1 pair rubber boots, 1 pair socks
__pperator C Head:
SCBA, surgical cap, cotton hood, plastic hood Hands:
1 pair cotton gloves, 1 pair orange rubber gloves Whole Body:
1 pair cotton coveralls, 2 pair coverall wet suits, 1 pair shorts Feet &
Ankles:
1 pair socks, I pair shoes, 1 pair plastic boots, 1 pair rubber boots
__pperator o Head:
SCBA, surgical cap, eye glasses, cotton hood, plastic hood Hands:
1 pair cotton gloves, 1 pair surgeon's gloves, 2 pair rubber gloves Whole Body:
1 pair shorts, 1 pair cotton coveralls, 2 pair coverall wet suits Feet &
Ankles:
1 pair socks, 2 pair shoes, 1 pair rubber boots, 8 pair plastic boots (right foot), 9 pair plastic boots (lef t foot) 1665 022 Page 16
FIGURE (1)
(cont.)
__pperator E Head:
SCBA, cotton hood, plastic hood Hands:
2 pair cotton gloves, 1 pair surgeon's gloves, 2 pair rubber gloves Whole Body:
1 pair shorts, 1 pair cotton coveralls,*1 pair paper coveralls, 2 pair coverall wet suits Feet &
Ankles:
1 pair socks, 1 pair shoes, 8 pair plastic boots, 1 pair rubber boots
__ Operator I Head:
SCBA, cotton hood, plastic hood, surgical cap Hands:
2 pair cotton gloves, 1 pair surgeon's gloves, 2 pair rubber gloves Whole Body:
1 pair shorts, 1 pair cotton co"eralls, 2 pair coverall wet suits Feet &
Ankles:
1 pair socks, 1 pair shoes, 1 pair rubber boots, 10 pair plastic boots
__pperator J Head:
SCBA, surgical cap, cloth hood, plastic hood Hands:
2 pair cotton gloves, 2 pair rubber gloves Whole Body:
1 pair cotton coveralls, 1 pair shorts, 2 pair coverall wet suits Feet &
Ankles:
1 pair socks, 1 pair shoes, 1 pair rubber boots, 10 pair plastic boots 1665 023 Page 17
Key To Figure (2) 6 I
a Eyes
^#"
^#"
R.lland L.lland Chest s
Gonads R. Knee L. Knee B
e a
Ch Os Ln R. Ankle L. Ankle C
Material Thicknesses Material
't hicknes ses DO 2
2 A
Over llody, mg/cm Under TLD, mg/cm l
Page 4
L d
2 3
R
)
2 )
(
9 t
1 e n r o u c e
g(
g i
a F
P 8
L 0
3 1
5 0
8 7
7 3
3 3
7 3
A na mero 7
F 3
7 3
P I
I 1
5 R
8 b
3
- &&U CNU l
1 D
e 7
8 2
2 2
e 4
2 3
8 7
2 2
2
)
2 )
(
t e n r o u c g(
i 0
F 2
0 5
4 e
7 2
g a
P 0
8 3
3 3
6 6
3 6
3 8
s 3
C 6
3 r
6 o
tarepo 5
7 0
4 7
- OOL CNO ssn s
e e
e C
4
~ w Nm M
D M
N D
A NA
%e e Nk O i
^
N C
i
<C' c
CD M
CC th C3 C.
M Om m
W m
m C3 et m
u m
C E
a C.
Am
-?
Cm 4
1665 027 e
6 3
2 4
6 3
J 6
3 2
)
2)
(
t en ro uc 2
g(
2 i
F e
g 3
4 7
0 a
P 1
3 8
0 6
8 8
3 6
8 6
8 8
s E
8 6
ro t
8 a
6 rep O
4 3
0 7
3 1
- OOLNsn3NO D
C
8 2
' e 8
2
)
2)
(
t en r o 3
uc 2
g(
i F
e 3
0 g
3 a
7 1
3 P
36 0
8 3
3 6
3 6
3 8
s 36 I
ro 3
t 6
arep O
3 7
1 0
3 3
DL Nm 1T
=
l
\\
j I
- !i2
t Figure (2)
(cont.)
?
Operator J 6
L
?
380 t
't 63 63 150 150 28 28 32 63 a
8 I
b 83 63 63 i
t CX
[
W L
330 33o CD e
b
(
i Page i
Page.
FIGURE (3)
Thicknesses of Protective Clothing In 2
'eg/cm Worn In Different Combinations By Individuals Entering the Make-Up Valve Room SCBA Face Mask 380 Shorts 20 (estimated)
Coveralls Cotton 32 Paper 4.6 Wet Suit 15.5 Gloves Cotton 28 Rubber 47 Surgical 23 Socks 30 (estimated)
Boots Plastic 13 Rubber (sides) 200 Rubber (bottom) 500 (estimated)
Eye Glasses 500 (esticated)
Masking Tape 10 (estimated)
=
)
e
FIGUFE (4)
Page,
Net Beta Response of Harshaw TLD 700 Chip (Ga=ma response subtracted) 6.0 A" ^\\ ' "
\\
Theoretical (Computer procram)
Experimental j
"h, 5
5.0 m
o w
E
~u m
g E
4.0 6
m i
O
-=
0 8
30 cez
.o e
o eo c.
8 2.0 c::
o 39 1.0 0
I I
0 100 200 300 400 500 9
Aluminum Shield Thickness, eg/cm~
1665 032
.sh*--
- w
%f**
a
,4_.gg,,
g g
r rount. vi Page.(
Entrance Rads
= Se sitivity Index for TLD 700 9.0 Rads d, posited in chip 8.0 7.0 x
Sr 90 6.0 a
y Coolant as of 9/28/79 x
5.0 D
?
E 4.0 3.0 a
-6 2.0 1.0 O
l i
i i
i i
I a
25 50 7j 100 125 150 175 200 J)apth In Abscrher, r::g/c::)
1665 033
Page.
I. - APPENDICES I)
Interviews With Individuals Involved In The Re; air Work In L e Make-Up Valve Room (enclosed)
~ '
II)
Sketches Showing Dimensions And Pipe Layout In The Make-Up Valve Room (enclosed)
III)
Calibration Certificates For The Survey Instrument "Teletector" Used To Survey The Ga=ma Field In The Make-Up Valve Room Prior To Entry For Repair Work (enclosed)
IV)
Photographs Of The Mock-Ups Performed To Re-enact The Entry Into The Make-Up Valve Room And The Work Done On The Valves (enclosed)
V)
Medical Evaluations Of The Overexposures By The Met-Ed Medical Consultant. Medical Evaluation Of The Inherent Shielding Of The Gonad (enclosed)
VI)
Late History Of The Make-Up Valve Room Investigations (approxi=ately September 8 to October 25, 1979) (not enclosed)
VII)
Early History Of The Make-Up Valve Room Investigations September 7,1979 (not enclosed)
VIII) Overexposure Letter To Each Of The Six Workers (not enclosed) 1665 034 t
e e
DOSE ASSESSMENT FROM THE AUGUST 28, 1979 ENTRY INTO THE TMI UNIT II FUEL HANDLING BUILDING NORTH MAKE-UP VALVE ROOM APPENDIX I Interviews With Individuals Involved In The Repair Work Done In The MU Valve Room 1665 035
TO:
File (14-Sept-79)
SUBJECT:
Interview with H.P. Foreman: Description of Nor.th M-U Valve Room Entry of August 28, 1979 (Revised 8-Oct.-79)
~
That morning I checked the Aux and FH Building instrument panels for venting problems, the flow seemed normal. At approximately the same time, an assistant was going over the old survey data from March 23, 1979, five days prior to the accident.
It looked like a primary water valve had not been repaired, the water was leaking at 255 ml per minute near MU-V-17.
Decided to enter North Valve Room to check for leak, no leaks had been seen in South Valve Room in July. Got H.P. Gerry Spires to go with me (he stayed out in the corridor) and I entered the valve room approximately 9:30-10:00 A.M., at 10:10 A.M. air sample was finished.
Entered part way in toward MU-V-255, could see leaks in MU-V-155 and MU-V-233A when surveyed. The air sample read about 1X10-8 mci /cc.
Dose rate of 15R per hour on MU-V-155, near the packing, using a teletector. The general area was 10R per hour, a steady field throughout the room. MU-u-233A showed 10R per hour near the packing. The water on the deck towards the drain read 10-12R per hour as well.
Left the room with teletector and checked with the H.P. who had stayed in the corridor near the entrance to the valve room for safety, and then went back into the room to look at the valves again so that I could draw a picture from memory, also to rt:rieve air sample, it was 10:20 A.M. My total time in the room was 1 to 1 3/4 minutes with dosimeter readings at about 265mR using two SR dosimeters. Notified the Operations people of what was leaking. At that ttse Mr. M-11eavy and Mr. Neely, FRC, got involved and decided that a crew would go back in to repair the leaks.
Ecd people enter within one hour, reported that MU-V-233A had been leaking at about 500 ml/ min and that they had secured the total packing so that it was just dripping.
In the middle of the af ternoon one man went into the room to stop the leak.
At approximately 4:00 P.M., I returned to the room to retrieve the air samples 305 and 328, in the FH Building, and inspect valve leaks. MU-V-155 was still leaking through the packing.
I was in the room for approximately 30 seconds. Read 100mR on personal cosimeter. (NOTE: no analysis e.. data was found. The sample log book showed 305 #6 and 328 #4 to read 600 mrad and 2 RAD respectively).
16,65 036 App. I Page 1 of 7
After coming out that afternoon, another crew was sent into the room at 8:00 P.M. to fix the leak on MU-V-155.
The leaking on MU-V-155 was a steady drip, no puddle. The floor next to this valve room reads 25R per hour so I expected this area to read the same.
The dose rates were so even around the room, I did not consider that there would be a problem.
The men who went into the room to fix the valve wore two wet suits of heavy rubber and one set of cloth under the wet suits. The inner wet suit was dry but the outer suits were quite wet.
They read 2R per hour gamma with the teletector.
Noted about 50R per hour b* eta (did not specify instrument for this reading).
I do not know where their badges were on their bodies since badge placement is not uniform.
MU-V-155 looked like it-had been leaking for a long time but MU-V-233A looked like the leak had originated 8 to 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> before original entry, somewhere between 8:00 PM, 8/27 and 8:00 AM, 8/28.
I was amazed to see a leak of such magnitude as that of MU-V233A.
I have a gut feeling that this may have been a very tiny leak for awhile but had developed into a large one over a short period of time.
I was the only one in the room more chan once.
Primary coolant is in the one inch, 2-inch, and four inch lines, and in the MU-Vs.
I did not observe any heavy deposits indicating old leak residues on piping.in general although I did not look at all the piping very carefully. Did see a few white spots (boric residue) near ~ low drips.
Should s
be able to see floor drain ir. glossy of print #160.
Should check plant specs for detailed piping composition.
Am sure that the floor drain position shown in the drawing is too far away from MU-V-155.
The water appeared to be running down pipe and wall then towards drain.
No actual " puddles" seen.
I may be reached at Unit II H.P., ext 8093.
1665 037 App. I Page 2 of 7
NORTH MU VALVE ROOM ENTRY 28-AUG-79 OPERATOR C (H,K,) INTERVIEW 4-0CT-79 1.
Dressed out in protective clothing and dosimetry as depicted on the attached sheet. He was pretty sure that the TLD was not covered by the SCBA Regulator.
2.
Entered.the MU V!'
.o-looking for the leaking valve (-12 sec) 3.
He notieel t..at the ".;akt.g valve was MU-V233A, which was different from the e he was led to believe.
4.
He noticed
..mc there was some water on the floor and that there was a lot of boric acid on MU-V-233A and also on MU-V-135.
~5.
He stood on 2 " pipe and leaned across hand wheel to MU-V-154 and with crescent wrench in right hand tried to turn top nut on right side of MU-V-233 and then changed over to lef t side to tighten packing.
At first it did not budge. Finally nuts began to turn and tighten packing.
This did not stop leak completely (-120 sec).
6.
Next he gripped the hand wheel with both hands and with a great deal of effort began to turn the wheel (~90 sec).
7.
He exited the room immediately when informed by Operator D that his time was up (-6 sec).
8.
Figures 1 and 3 depict the two positions he was in while wort.ing on MU-V-233A cnd MU-V-154 hand wheel, respectively.
9.
The relative positions of his various body areas to potential radiation sources are depicted on the attached sheet.
1665 038 App. I Page 3 of 7
NORTH MU VALVE ROOM ENTRY (28 Aug 79)
OPERATOR D. (R.J.) INTERVIEW 4-Oct-79 1.
Worked with Operator C to stop leak on MU-V233A; Close MU-V-154, 2.
Suited up primarily by himself. Used two (500mR) self-reader dosimeters because H.P. Tech told him that they were all they had available. Did not think that the regulato'rs covered his dosimeters because it ras hanging low.
3.
Waited at the door to Valve Alley while Operator C worked on MU-V-233A and MU-V-154.
After Operator C exited Valve Alley, they discussed what must be done to stop the leak.
4.
Entered Valve All.ey and checked tags on other valves before going on to MU-V-154.
Saw a lot of Boric Acid along the length of the 4" pipe back to the wall. (~10 sec).
5.
While standing with both feet on the floor, gripped the hand wheel and tried to close MU-V-154.
(-60 sec).
6.
Stood on 4" pipe while straddling MU-V-155 Reach Rod and leaning back to jerk the hand-wheel was able to turn it and close MU-V-154
(~90 sec).
7.
When he thought his stay time was up, he exited Valve Alley immediately.
(~8 Sec.).
8.
Figures 4 and 5 depict the two positions he was in while working on MU-v-154.
'9.
The relative positions of his various body areas to potential radiation sources are depicted on the attached sheet.
lbVs vJ/
App. I Page 4 of 7
FORTH MU VALVE ROOM ENTRY (28-AUG 79)
OPERATOR E:
INTERVIEW OC1-79 1.
Entered North valve room and went directly to MU-V-233A. (~6 sec).
2.
Stood with right foot on 2 " pipe and left foot on Reach Kod directly above MU-V-155.
While in that position, leaned
- across hand wheel of MU-V-154 to tighten packing not on MU-V 233A with crescent wrench
(~120 sec).
3.
Changed foot positions with right foot on Reach Rod d'irectly above MU-V-155 and lef t foot on Reach Rod at the wall. Gripped hand wheel to turn (close) MU-V-154 (-60 sec).
4.
Exited valve alley immediately. Did not remember seeing any water on the floor.
5.
Outside the room he checked himself for contamination after removal of his protective clothing and found none with the hand and foot monitor and portable survey meter.
6.
Figures 2 and 3 depict the two positions he was in while working on MU-V-233A and MU-V-154 hand wheel respectively.
7.
The relative position of his various body areas while performing these operations are as listed on the above page.
1665 040 App. I Page 5 of 7
NORTH MU VALVE ROOM ENTRY (28 AUG-79)
OPERATOR I (W.S.) INTERVIEW BY J. ROY 4-Oct-79 1.
Worked with Oper. J. Told'to go into valve alley and stop leak on MU-V-155.
2.
Understood what his task was.
Had been in that area several times before.
3.
Had been briefed by H.P. as to the radiation levels.
4.
Suited up primarily by himself.
Checked self reader dosimeters and confirmed that they were zeroed.
5.
The only item he carried into the valve room was a crescent wrench (10-12 inches).
6.
Entered the valve rcom with operator J at the door to relay signal from H.P. Tech when his 3-4 minutes stay time up (~ 6 sec.).
7.
He noted MU-V-155 was leaking (oozing) and the floor was wet from MU-V-155 to floor drain near MU-V-273.
8.
Began working on MU-V-155 by squatting all the time (~ 120 see) a.
Had to clear boric acid off R Nut; L. Nut was clean b.
Inspected packing with arms resting on his knees.
c.
Flipped the wrench from right to left nut to tighten packing.
d.
About 2/3 way thru operations he leaned in close to the valve to count the threads.
Both hands around the valve.
Eyes about 6" away fram valve.
Remained in this position until tapped on the shoulder by operator to indicate that his stay time was up (~30 sec) 9.
Exited valve alley with Operator J immediately (~6 sec).
10.
Outside the room, checked his SR dosimeter (wrist) and wasn't surprised to see that it was pegged ( > 500 mR).
11.
Discussed with Operator J. how to approach the problem of finishing the job of stopping the leak from MU-V-155.
Stayed at the door to notify Operator J. when H.P. Tech signaled that his stay time was up.
12.'
Went in and tapped Operator J. on the shoulder when his time was up.
They both exited immediately ( ~12 sec).
13.
Af ter removal of protective clothing, frisked himself and d
't recall being contaminated.
14.
Recalled that he had several high exposures already on his TLD from other RWP's ( 200nR) 15.
Figures 6 and 9 depict the two positions he was in while working on MU-V-155 and inspecting it, respectively.
16.
The relative positions of his various body areas to potential radiation sources are depicted on the attached sheet.
I665 04i App. I Page 6 of 7
NORTH MU VALVE ROOM ENTRY (28-Aug-79)
OPERATOR J (D.S.) INTERVIEW BY J. ROY 4-Oct-79 1.
Worked with Operator I.
Told to go into valve alley and stop leak on MU-V-155, 2.
Understood what his task was.
Had been in that area before sevcral times.
3.
Had been briefed by H.P. as to the radiation levels.
4.
Suited up primarily by himself.
Noted that his self. reader (wrist) had about 150=R on it before going into valve alley.
5.
Waited at the door. to Valve Alley while Operator I worked on MU-V-155.
When signaled by the H.P. Tech, went in and tapped Operator I on the back to indicate that his time was up, they both exited immediately (this took about 12 Sec.)/
6.
After discussions with Operator I went into valve alley and immediately began to work on MU-V-155.
Used crescent wrench to tighten nut on both sides while standing near reach rod (~ 72 sec).
7.
He squatted to inspect packing on valve. His knee TLD's always faced the pipes or MU-V-155 ( ~30 sec.).
Remained in this position until tapped on the shoulder by Sawyer to indicate that his time was up.
8.
Exited Valve Alley with Sawyer immediately (~ 6 sec).
9.
Outside the room checked his SR dosimeter (wrist) and noted that it was pegged (>500 mR).
10.
After removal of protective clothing, frisked himself and didn't recall being contaminated.
11.
Additional Comments
.a.
Had whole body count the next day.
Didn't know results yet.
b.
Recalled that he had several exposures on his TLD on previous RWP's during the month.
c.
Submitted a urine specimen next day.
d.
Knows that his TLD was covered by his SCBA regulator at least part of the time.
12.
' Figures 7 and 10 depict the two positions he was in while working on MU-V-155 and inspecting it, respectively.
13.
The relative positions of his various body areas to potentia' radiation sources are depcited on the attached sheet.
1665 042 App. I Page 7 of 7
..>cSSMENTFROM THE FUEL AUGUST HANDLING 28, 1979 BUILDING ENTRY NORTH INTO MAKE-UPVALVE i
4 6
APPENDIXII Sketches Layo t Showing u
Dim In en io s
The ns MU And Valv Pipe e
Room
- ga
=-_,,
t
'i.
L.3 D
Me)
THI UNIT II FUEL IIANDLING BUILDING NORTil MAKE-UP VALVE R00H Floor Plan 6
9 s
W. eJ M
- it 19' 6" h
. i'..'*;,.?.,<:'s s' ry.o..?; no :st,3;*;. A ;..,, y,t j,q.s...... 2. s>.s.g..p.r,?. h.;'. : : c.;e scy:.Q:Mc -; cf..,,
a t
.,[
W 'I'U~V233^
1"-Pipe-P l
21s -Pipe gl r Drain U.V,} 5':
u
'7, '
_ygy 4" Pipe g
a f
I l
HU-V2 IU-V-273 1.,
' s Sfi.i.,Qh l Work Arya b
+
?,hdi.c...f.p....
i 1,
7,,
m
/
e
)
\\l
/
i
./
'I l
1r
'-i..
g
.c.. ue5c1c wra.*-y.Mswg aeg etl' \\t6di Cde' 9f: c
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'c'^W "*~ *' **!.i i.
- .awz...
- c.y g y: -
i thbu wall thru wall
Q AT
- ; H 1 '4 I.s/ 3y;"O'r *, )2 Pipe a t 9 ' 7,"
Elevation
. Work area indicated by dotted lines. The larger dotted area indicates position of body. Smaller dotted area indicates position entered only by hands and arms.
ON LT1 CD 4
4 App. II Page 1 of 2 1
TMI UNIT II FUEL llANDLING BUILDING NORTil MAKE-UP VALVE ROOM Elevation /Section e.
0 0
(<
9 M
0 9
$5'50 k e)
V4 b
Work Area b
9' 7" o
j o
y Elevations Above Floor
~~~~~-
8'4" llandle for MU-V 154
-f><l-- b)
MU-V 23 5' 7" m
Ch 1" Pi ne Ln
~
- 21" Pipe 21 " Pipe
.- g s
HU-V154 5
3' 10 "
4 U1 o Reach rod 3/4" 4" Pipe Scale 3/8" =~1 foot P. pe Dimensions shown are size of pipes 21 _,,s ___P114 1,
7,,
MU-V155 4" Pin e f
l '--3" 8
Rod f
- @ Mil-V273 Reach o
MU-V 272 Reach Rod g Floor Drain
,........ m non.q,..g,,..,..,..----,...,....,,..
,., p
, Pa n 2 of 7
'f Ann. TT
DOSE ASSESSMENT EA0M THE AUGUST 28, 1979 ENTRY INTO THE TMI UNIT II FUEL HANDLING BUILDING NORTH MAKE-UP VALVE ROOM APPENDIX III
. Calibration Certificates For The Survey Instrument "Teletector" Used To Survey The Ga=ma Field In The Make-Up Valve Room Prior To Entry For Repair Work 1665 046
Portct Gert2 Censultants, Inc.
76 RITTENHouSE PLACE AnouoaE.PA.isoo3 November 30, 1979 215496-5353 The calibration of the Teletector utilized on September 28, 1979 was current as per the enclosed July 22, 1979 certificate. An operational check was made in a known field of 80 mR/hr. with this Teletector survey meter just prior to initial entry into the Make-Up Valve Room on August 2S, 1979.
The calibration certificate dated September 11, 1979 was compiled af ter the valve room entry on August 28, 1979. The certificate indicates that the instrument was not operational on the date of calibration and therefore, no calibration data is available for it after the entry date.
Further checking revealed that the instrument was inoperative because it had been dismantled during the decontamination procedure that followed use of the instrument during the valve room survey. The high range GM tube in the instrument was also changed before re-assembly and recalibration.
1665 047 App. III Page 1 of 3
App.III, Page 2 of 3 FOP?. RS ~
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[
U\\.g/ (J
_A ma Sen/ ices Inc.
( g, km ja Q
g "This Certificate will be accompanied by Calibration Charts or Readings where applicable
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_ _ _ = _
INSTRUMENT INFORMATION CUSTOMER INFORMATION
~
Cuatc=er Us::::: I/.I/?6E' )I/4/F" D//9/16 Instruncnt Hanufn,cturer '[Fldf72R SC Model 6 // 7- [5 Scrial Nu=ber ('4.9 usto=er Address:
External Probe (s)
_ Serial #
Calibration Method (.'s e ;' 7 5/ /(PJ-
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Cus tc=er P.O. J Service V.O. 3
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STATD'ENT OF CERTIFICATION
~
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.a Cortify that the instrum ent listed above.:as calibrated and inspected prior to shipment and
- hat it met all of the Manufacturers published operating specifications. Ve further certify
- hat our Calibration Measurementa are traceable to the National Bureau of Standards (Uc are tot respo cible for dnaage incurred during shipment or use of this instrusent).
n':trument' Calibrated by: Oh I certify that the above information is n
fh j(Si;ned)
/
1665 048 correct:
f lalibraticen Date:
'7/.2./ 7 Authorized Ar.cnt
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INSTF.UMENT INFORMATION Oustc=er Name:
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Oustocer Address:
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TNSTRNNT CALIBRATION INFORuATION
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STATEMENT OF CERTIFICATION a Cortify that the instrument listed above was calibrated and inspected prior to shipment and hat it nat all of the Manufacturers published operating specifications. We further certify hat our Calibration Measure =enta are traceable to the National Bureau of Standards (We are ot responsible for de= age incurred during shipment or use of this instrument).
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Authorized Agent t Calibration Due:f t.// /pp Titic Date f
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DOSE ASSESSMENT FROM THE AUGUST 28, 1979 ENTRY INTO Tile TMI UNIT II FUEL HANDLING BUILDING NORTII MAKE-UP VALVE ROOM APPENDIX V Medical Evaluations Of The Overexposures By The Met-Ed Medical Consultant. Medical Evaluation Of The Inherent Shielding Of The Gonad. 1665 063 9
r REMS CORPORATION pI lr f r '] l. 3004 La B.'ancha St. NW Albuquerque, New Mexico 87104 (505) 243-0236 r-. ,-- R _ = -- -a=- Fred A. Mett:er Jr., M.D., M.P.H., President {/ . November 14, 1979 r E L n,, n o C L Porter-Gert: Associates 76 Rittenhouse Place Ardmore. Pa.
Dear Sid:
Thanks for your call today regarding T4I. I have done a bit of research regarding the strontium dosimetry problem that you have. In any measurements of tissue one has to be careful that the calculations are made on living people, preferably in the position of interest. Most measurements derived from anatomy books are derived from cadavers and are suspect. I have therefore reviewed ultrasound scans of the testicle made on young males. These are made usihg 5 MHz sound waves. Tne subjects are in a sitting position with the scrotum immersed in a water bath. The results indicate that the thickness of tissue from the outside of the scrot m to the seminiferous tubules in the dependent portion averages 3mm. This includes the tunica. For your interest I have included a scan on a patient with a normal testicle on theright and a swollen testicle on the left. The left testicle also has an abnormal fluid collection around it which permits separation of the tunica and the scrotum so that both are visualized. In addition today I did a scan on a cadaver specimen which indicated as we suspected that the tunica is almost imm in thickness. The average testicular size in normals was 3X3X5 cm. The density of tissue can be assumed to be approximately 1 gram per cubic centimeter. I hope that this information is of some use to you and to Metropolitan Edison. If I can be of more help please do not hesitate to call. Under separate cover I will be sending you some information concerning medical treatment of patients with internal contamination due to strontium. Sinc 'ely; O Fr d A. Mettler Jr. M.D. 1665 064 Supplies On Site Training and Courses Nuclear Medical Consultation 4. 17 Daaa 1 af f.
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A REC [iVE0 ' .c2.G.,/977 d ~,(,l Eift!!ENT/ Ly;a.:rr:;r:t 433g33;;37 g.ggp FORTER GERiz cc,s3gty;,qr3 g3g-q%qg'e p0UN0@fffN Y p 47 UJ Noverrber 21, 1979 0 Mr. R.W. Heward Panager, Fadiological Controls for DE #2 Recovery METPOPOLIrd EDISCN COMPANY P.O. Box 480' Middletcwn, PA 17057
Dear Mr. He.ard:
PRESIDENT This is in response to your ?etter (telecopied Noverbar 21, 1979, with attachment to this letter, "St:rary of Ecses to n!I-II Workers in the Make-up Valve Alley of the Fuel Handling Building on August 28, 1979" by Porter-Gert:: Consultants, Inc.) The document is unsigned. Ycu have' asked me to give ycu a medical opinion regarding these exposures. I am unable to identify which of the eleven wrkers I saw gn August 30, 1979. Asstrning the dose calculations are correct as stated, I find that in all cases the skin deses have exceeded the quarterly limits as per 10CFR Part 20. I would not have expected these doses at the time they wre received to have caused any evert clinical signs or symptcms. I muld not expect these doses to { result in any clinically detectable radiation damage, e.g., cancer,in the future. ~ 'Ihe gonadal doses are withm the limits specified in 10CFR Part 20. In my cpinion these doses also should not result in ' 190ng GR J l NtJI u , Uti any, detectable damage new or in the future. R derence the letter addressed to Mr. Elwin E. Clerrents dated unwrasm cm Niverrber 21,1979 (draft) : In paracraph 4 delete " physically eta:: tined", as I do noE_ recall physically examining this tran sciruct crurra. ..(ddifically. bbrdiEg to the dose e!stirrates given in paragraph 2, you may T - [ ~ 350s MARKET STREET idelude a statement in paragraph 5.... PHILADELPHIA. PA 191C4 (2:42n2m "According to the dose estinates in paragraph 2 above, the exposure to the skin has exceeded the Federal quarterly limits. The exposures to 1665 066 the skin are medically insignificant, and I cb ~ not expect any clinically detectable darrage from this radiation exposure ncw or in the future." . 4 -e.+. Op/-:~n. o. y~ e : m t/iMr8 Onsid@w.F.?YT756??:: 4d. M %'915;xc.e.y+sSks-MMgif':W...s-s we. ~ m h-; T+ s .e...,.,p 2.v.% 1e 5: 'f.t.t. . ~; M.%.t-:p.:.:.
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Mr. R.W. Ece.ntd !;ovcd.>2r 21,1979 Page '1%o q q -- ateijb ~ You ray insert this paragraph in the appropriate letters to hd the employees and send them to tre for signature. .rr
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"..). For your inferration, I received a telephone call frcm Mr. Porter 0) on Octcher 23, 1979 stating I v.ould have these dose esticates by October 29, 1979. y I hope this is satisfactory. c '.- ely, %pOAvam _ hM . Linnerann, M.D. REL:sk 1665 067 2- .=,. . -== .q .. i.- %^* 6 d ' ; %- f r. -
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Mr. R.W. He.ord Fanager, Padiological Controls for 'DiI #2 Recovery ~
- ETEPOLITAN EDISCN CWPANY P.O. Box 480 Middletcwn, PA 17057 RE_: Visit to Three Mile Island en August 30, 1979 PRESIDENT
Dear Mr. He.ard:
According to the records in my files, en August 30, 1979 I was asked to visit Three Mile Is1r.d to exa-ine five employees who were overexposed to radiation. I.sn s a t T: C from 3:30 to 6:00 p.m. 2e examinations were at the request of Dick Dubiel. History: Khile repairing a leaky valve in de pri ary m llan: circuit, five employees were expcsed to radiation. 'I~ney were wearing anti-C clothing and self-cont ined respirators. They had TID dosimeters on various parts of de bcdy, including the anterior portion of the tibia and t' e chest and ankles. The clothing was in tact; and the skin was no; directly con-taminated with primary coclant that leaked frca de valve. 'Ihe emersion gama dose was 15 P/ hour. They were allcwed to stay in there ap,r oxi: ately 4 :.'.inutes. An cvere:;csuru -ar o ahnl1d l, was first detected on examination of the TCs, which shcved N010iJ an increased beta dose. The highest dese to de 'e:s was 00 Y 01n.M resorted to de oa ene =isht 1ower 1es or c=e e v1czee 143 re=: and the highest dose on the body was to the r.:2rior chest of another employee, 30 ren. Ga.Ta dosi eters reccrded apprc:(- irrately 650 to 750 millirem. UNIVERstTY CITY scitucf CENTER 'Ihe whole body Counting was unrr.rkable. None of de five erployees had any signs or sy:Tptors of otere:c: oste e to radiation. Their rain concern was anxiety aboc.t t.e dose by 1s : MARKET STREET themselves, their families and the press. Or eva-inaticn cf 22 PHluCELPHIA. PA 19104 ski.n they reported no evidence of reddeni.g of de ski. o.. D85) 283M any part of their body. Examination of de skin of de legs of the two errployees with highest re;orted deses on this date was negative. Continued.... 1665 068 App. V Page 5 of 6
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F. Mr. R.W. H ward Nove:rber 21, 1979 Page T.o D P, Ng 0$$gq F.y impressions at this tirre were:
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- 1) Possible skin overextosre to beta radiation 3
according to the bad'e readings. g
- 2) No evidence of significant garca e scs=a according to badge readings.
- 3) E:gosure to the skin, i# correct acccMing to badge readings, is not :adically sig-i'icr.t now or in the future.
My recorr.endations were:
- 1) 3 days of urine and fecal bicassay.
- 2) Analysis of the source of radiation 20 e:glai. the high energy betas necessary to pancrate 3 layers g
of clothing and tape cver the badge.
- 3) Plant should send rne final dose acs:ssr.r.ts as socn as they are availaole.
- 4) No further bicassay testing par. ding fi.al dose assessrents.
cccrent: I spent approxi:ately two hcurs with tha five emple;aes discussing the biological effec':.s of radiation, partic.:larly as it pertains to the skin. I erghasized the large doses (apprc>:- irately 600-800 R) required to develop a te pcra:'1 erfthe a, and that cancer of the skin due to radiatica ed.posure has not been documented, unless a previous chronic radicdacaritis had developed. Tnis latter does not occur si:n.he deses received. I hope this is satisfactory. /. f3 S1:- _ely,( [ 1,. ._. y.,_.7.. 1; 0d h :'tp,,. a n ~ Q bgef5. DtEran., :'.D. G' 1665 069 App. V Page 6 of 6 ._}}