ML20150C758
| ML20150C758 | |
| Person / Time | |
|---|---|
| Issue date: | 10/31/1978 |
| From: | Brooks B NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA) |
| To: | |
| References | |
| NUREG-0463, NUREG-463, NUDOCS 7811270034 | |
| Download: ML20150C758 (50) | |
Text
_ _ _ _ ________-._.
NU R EG-0463 OCCUPATIONAL RADIATION EXPOSURE Tenth Annual Report 1971 Barbara Brooks Manuscript Completed: October 1978 Date Published: October 1978 Division of Technical Support Office of Management and Program Analysis U. S. Nuclear Regulatory Commission Washington, D. C. 20555 7S //a70 o W j
TABLE OF CONTENTS Page ABSTRACT...............
iii INTRODUCTION..
1 I.
ANNUAL REPORTS Exposure Distributions......
3 Man-rems per Licensee Type.........
7 Commercial Nuclear Power Facilities................
7 Industrial Radiography Operations.............
18 Fuel Processors and Fabricators...........
18 Manufacturers and Distributors...
22 II.
TERMINATION REPORTS Terminations, 1969-1977....
24 Transient Workers, 1969-1977...............
24 Career Doses.....................................
26 III.
PERSONNEL OVEREXPOSURES Types of Overexposures.
30 Summary of Overexposures, 1971-1977....
31 TABLES 1.
Distribution of Annual Whole Body Exposures by Licensee Category, 1977........
4 2.
Summary of Annual Whole Body Exposures for Covered Licensees, 1968-1977...............
6 3.
Man-rems Accumulated by Category of Covered Licensees, 1973-1977.........................
8 4.
Summary of Annual Exposures Reported by Nuclear Power Facilities, 1973-1977...
10 5.
Pressurized Water Reactors Listed in Ascending Order of Man rems per Reactor, 1973-1977.....
14 6.
Boiling Water Reactors Listed in Ascending Order of Man-rems per Reactor, 1973-1977......
15 7.
Percentages of Personnel Dose by Work Function.....
17
1 ii TABLE OF CONTENTS (continued) 1 Page 8.
Radiography Firms Listed in Ascending Order of Average Dose Per Worker....................
19
- 9. <
Fuel Fabricators and Processors Listed in Ascending Order of Average Dose Per j
Worker..
21 10.
Manufacturers and Distributors Listed in Ascending Order of Average Dose Per Worker..
23 11.
Transient Workers, 1969-1977.................
25 12.
Summary of Overexposures to External Sources of Radiation....
32 FIGURES 1.
All Reactors, Values of Man-rems, Megawatt-years, Workers...........
11 2.
PWRs and BWRs, Values of Man-rems, Megawatt-years, Workers..............
12 3.
Average Career Doses...........
.............. 29 APPENDICES Appendix A - Annual Whole Body Exposures at Licensed Nuclear Power Facilities, 1973-1977................
35 Appendix B - Overexposure Summaries............
..... 40 Appendix C - Career Doses for Radiation Workers Terminating During the Years 1969-1977.......
44
ABSTRACT This is a report by the U. S. Nuclear Regulatory Commission on the operation of the Commission's centralized repository of infonnation on the exposure of personnel to radiation.
The report is published annually and is available at all NRC public document rooms or may be purchased from the Nationel Technical Information Service in Springfield, Virginia.
The bulk of the information sunmarized in the report was obtained from annual and termination reports (Sections I and II) submitted by four categories of NRC licensees:
(1) operating nuclear power reactors; (2) industrial radiographers; (3) fuel fabricators and processors; and (4) commercial processors and distributors of specified quantities of bypro-duct materials, in accordance with the requirements set forth in Part 20.407 and Part 20.408 of Title 10, Chapter 1, Code of Federal Regulations.
Annual reports were received from 457 covered licensees which indicated that 98,212 individuals, with an average annual exposure of 0.40 rems, were monitored during 1977.
The number of termination reports submitted by these licensees continues to increase.
Personal identification and exposure information has been taken from about 245,000 reports and incorporated into the repository during the ten years that it has been operating.
iv Information on incidents involving personnel overexposures to radiation or radioactive materials (Section III) was obtained from reports submitted by all NRC licensees pursuant to Parts 20.403 and 20.405 of Title 10, Chapter 1, Code of Federal Regulations.
The total number of over-exposures reported in 1977 decreased from the number reported in 1976, but is about the same as that reported in previous years.
The number of incidents reported by radiography firms, however, is considerably less than last year's values.
The more significant overexposures which occurred in 1977 are summarized in Appendix B.
l l
i
TENTH ANNUAL OCCUPATIONAL RADIATION EXPOSURE REPORT 1977 INTRODUCTION On November 4, 1968, the U.S. Atomic Energy Commission (AEC) approved a program for the reporting of certain occupational radiation exposure information to a central repository.
This information was to be required l
of four categories of AEC licensees, as defined in 10 CFR 20.407, and of AEC facilities and contractors exempt from licensing.
As of December 31, 1973, radiation exposure information on approximately 150,000 occupationally exposed persons had been incorporated into the repository.
Annual reports for each of the years 1969 through 1973 summarized this information and were published as six separate documents (WASH-1350-R1 through WASH-1350-R6).
In January 1975, with the division of the AEC into the Energy Research l
and Development Administration (ERDA) and the U.S. Nuclear Regulatory i
Commission (NRC), each agency assumed responsibility for collecting l
l and maintaining occupational exposure information reported by facilities ur. der its own jurisdiction.
Beginning with the annual report for l 0perating nuclear power reactors; industrial radiographers; fuel pro-cessors, fabricators and reprocessors; commercial processors and distributors of specified quantities of byproduct material.
I 1
l l
_ calendar year 1974,2 the NRC's publication no longer contains information pertaining to ERDA facilities or contractors.
Comparable information for
)
i ERDA, now Department of Energy (DOE), facilities and contractors is collected by DOE's Division of Operational and Environmental Compliance at Germantown, Maryland.
l l
2The annual occupational radiation exposure reports for NRC licensees for 1974, 1975 and 1976 are available from NTIS as NUREG 75/108, NUREG-0119, and NUREG-0322.
The annual radiation exposure reports for DOE /ERDA contractors for 1974, 1975, and 1976 are available from NTIS as ERDA-76/119, ERDA-77-29, and DOE /EV-0011/9.
I.
ANNUAL REPORTS - 10 CFR 20.407 Exposure Distributions On February 4, 1974, 10 CFR 20.407 was amended to require the four categories of covered licensees to submit an annual statistical report l
indicating the distribution of the whole body exposures incurred by their employees.
In prior years the annual report was formatted differently and was not very useful as a basis for estimating man-rems.
Table 1 is a compilation of the statistical reports submitted for calendar year 1977.
It shows the number of individuals that incurred a cumulative annual whole body dose that fell within one of the 18 dose ranges, and the percentages of the total number monitored in each range.
It also shows the cumulative dose (man-rems) estimated to have been received by these individuals.
This number was obtained by assuming that each individual received an annual dose equal to the mid point of the dose range in which he appears, and by then summing these doses.
The table shows that 39% of the 98,212 individuals monitored during 1977 received exposures that were too small to be detected by personnel radiation monitoring devices, that 99.7% of the exposures were less than 5 rems, and that 94.8% of the total number of man-rems were accumulated by i
individuals with annual doses of less than 5 rems.
l All of the figures compiled in this report relating to exposures and/or doses are based on the results and interpretations of the readings of various types of personnel monitoring devices employed by each licensee.
This information obtained from routine personnel monitoring programs is sufficient to characterize the radiation environment in which individuals work and is used in evaluating the radiation protection program.
How-ever it may not be directly suitable for use in the assessment of risk to the individuals involved.
1
m. - - _ _ _
i a
TABLE 1 DISTRIBUTION OF ANNUAL WHOLE BODY EXPOSURES BY LICENSEE CATEGORY 1977 I.
E xposure Range s (Rems)
Category of NRC Total No.
t.ess Than Measurable 0.10-0.25 0.54 0.75-Ucensee Monitored Measurable
< 0.10 0.25 0.50 0.75 1.0 12 2-3 3-4 45 56 67 78 8-9 9-10 10 11 11-12
> 12 POWER REACTORS f
W. of Individuals 71,904 27,671 15,523 6,750 5.179 3,300 2.500 6,174 2,838 1,130 569 141 66 36 21 6
%in Range 100%
38%
22%
9%
7%
5%
A 9%
- 4%
2%
4------
i%--
No. of Man-remt 32,731 0
776 1,181 1,942 2,062 2,188 9,261 7,095 3,955 2.560 776 429 270 179 57
%in Range 100%
2%
4%
6%
6%
7%
28%
22%
12%
8%
2%
1%
1%
--1%
RADIOGRAPHY 950. of Indmduals 10,569 4,372 2.488 1,084 812 512 357 644 192 63 30 12 1
1 1
%in Range 100%
41%
24%
10%
8%
5%
3%
6%
2%
4-.
. i s -_.. - - -
- - _ - -_--~_
8 27 No. of Man-rems 3,159 0
124 190 305 320 312 966 480 220 135 66 6 n
%in Range 100%
4%
6%
10%
10%
10%
31 %
15%
7%
4%
2%
4___
____.._--____is
+
i FUEL F AB. & PROC.
No. of Individuals 11.496 4,492 4.533 1,057 571 315 179 205 91 28 25
%in Range 100%
39%
39%
9%
5%
3%
2%
2%
1%
Olo. of Man-rems 1,725 0
227 185 214 197 157 307 228 98 112
%in Range 100%
13%
11%
12%
11%
18%
13%
6%
7%
t
}
MANUF. & DISTRIB.
9^a, of Individuals 4.243 1,784 1,271 394 215 144 91 153 76 47 g
g
%in Range 100%
42%
30%
9%
5%
3%
2%
4%
2%
1%
m ___
4-__
No. of Man-rems 1,329 0
63 69 81 90 80 229 190 165 153 88 91 30
%in Range 100%
5%
5%
6%
7%
6%
17 %
14%
12%
12%
7%
7%
2%
TOTALS No of Individuals 98,212 38,319 23,815 9,285 6,777 4,271 3,127 7.176 3.197 1.268 658 169 81 41 21 6
1 100%
39%
24%
10%
7%
4%
3%
7%
3%
1%
1%
____,g____
__ _s,
%in Range Gio. of Man-rems 3'4,944 0
1,190 1,625 2,542 2.669 2,737 10,763 7,993 4.438 2,960 930 526 308 179 57 27
%in Range 100%
3%
4%
7%
7%
7%
28%
. 21%
11%
8%
2%
1%
4____--_is____ _ _ _ _ ___ -__ _ _ _ _ _ _.. _ _ _ _ _,.
-_.- It should be pointed out that very few of the annual exposures that exceed five rems are classified as personnel overexposures.
Although 1.25 rems is the quarterly limit set forth in paragraph (a) of 10 CFR 20.101, paragraph (b) permits licensees, under certain conditions, to allow a worker to receive a whole body dose of three rems per calendar quarter (up to 12 rems annually).
The conditions are that (1) the licensee must have determined and recorded the worker's prior accumulated occupational dose to the whole body, and that (2) the worker's whole body dose when added to his accumulated occupational dose does not exceed 5(N-18) rems where "N" equals the individual's age in years.
Although there is no annual limit, annual exposures that exceed 12 rems indicate that an overexposure has occurred.
Any quarterly whole body exposure in excess of the applicable quarterly limits are considered overexposures and must be reported. A discussion of various types of overexposures that have occurred is given in Section III.
A summary of the annual whole body exposures reported to the Commission by the four categories of NRC licensees required to submit reports during the past ten years is presented in Table 2.
One can see that about 95% of the exposures have consistently remained less that two rems, and that the number of individuals receiving an annual exposure in excess of five rems is about one half of one percent of the total number of individuals monitored each year.
T
TABLE 2
SUMMARY
OF ANNUAL WHOLE BODY EXPOSURES FOR COVERED LICENSEES 1968-1977 Percent of Percent of Number of Total Number Exposures Exposures Annual Exposures Year Monitored
< 2 Rems
> 5 Rems
> 12 Rems 1968 36,836 97.2%
0.5%
3 1969 31,176 96.5%
0.5%
7 h
3 1970 36,164 96.1 0.6%
0 1971 36,311 95.3%
0.7%
1 1972 44,690 95.7%
0.5%
8 1973 67,862 95.0%
0.5%
1 1974 85,097 96.4%
0.3%
1 1975 78,713 94.8%
0.5%
1 1976 92,773 95.0%
0.4%
3 1977 98,212 94.5%
0.3%
1
I Man-Rems Per Licensee Type As was previously explained, the statistical data contained in the annual reports required by 10 CFR 20.407 permit an estimate to be made of the man-rems accumulated by the individuals monitored by each licensee.
The information submitted by each one was collated to yield the informa-tion shown in Table 3.
There are two values indicating the average annual exposure per individual.
The lower values were obtained by dividing the total number of man-rems by the total number of individuals monitored, and the higher values were obtained by dividing the same total number of man-rems by the number of those individuals reported as having received a measurable exposure (referred to as radiation workers).
The latter average is normally used for radiation workers because it delbtes the minimal' exposures of many individuals who are monitored for convenience or for identification purposes.
In 1977 the average exposure for workers continued to decline in every category except power reactors, where it remained about the same.
The averages consistently remain less than one rem per worker.
Commercial Nuclear Power Facilities The percentage of the total number of man-rems incurred by workers at power reactors has, during the last five years, increased from 67% to 84%.
Therefore, this section of the report has been expanded to illustrate and discuss some of the factors contributing to this increase.
TABLE 3 MAN-REMS ACCUMULATED BY CATEGORY OF COVERED LICENSEES Average Dose Average Dose Covered Categories Number of Total No.
No. Individuals (Rems) Per (Rems) Per of NRC Calendar Licensees Individuals W;th Measurable Total No.
Individual (Based Worker (Based on Licensees Year Reporting Monitored Exposure Man-rems on Total Monitored)
Measurable Exposure)
- Commercial 1977 65 71,904 44,233 32,731 0.46 0.74 Power Reactors 1976 62 66,800 36,715 26,555 0.40 0.72 1975 54 54,763 28,034 21,270 0.39 0.76 1974 53 62,044 21,904 14,083 0.23 0.64 1973 41 44,795 16,558 14,337 0.32 0.87 Industrial 1977 339 10,569 6,197 3,159 0.30 0.51 Radiography 1976 321 11,245 6,222 3,629 0.32 0.58 1975 291 9,178 4,693 2,796 0.30 0.60 1974 319 8,792 4,943 2,938 0.33 0.59 1973 341 8,206 5.328 3,354 0.41 0.63 ce Fuel Processing 1977 23 11,496 7,004 1,725 0.15 0.25 and Fabrication 1976 24 11.227 5,285 1,830 0.16 0.35 1975 23 11,405 5,495 3,125 0.27 0.56 1974 25 10,921 4.617 2,739 0.25 0.59 1973 27 10,610 5,056 2,400 0.23 0.47 Processing and 1977 30 4,243 2,459 1,329 0.31 0.54 Distributien of 1976 24 3,501 1,976 1,226 0.35 0.62 Byproduct 1975 19 3,367 1,859 1.188 0.35 0.63 Material 1974 24 3,340 1,827 1.050 0.31 0.57 1973 34 4,251 1,925 1,177 0.28 0.61 Totals and 1977 457 98,212 59,893 38,944 0.40 0.65 Overah 1976 428 92,773 50,198 33,240 0.36 0.66 Averages 1975 387 78,713 40,081 28,379 0.36 0.71 1974 421 85,097 33,291 20,810 0.24 0.63 1973 443 67,862 28,867 21,268 0.31 0.74
- includes all reactors that reported, although all of them may not have been in commercial operation for a full year.
Table 4 summarizes the information contained in Appendix A, which was reported by each reactor site during the past five years.
The data are presented for the two types of light water reactors-pressurized water reactors (PWR) and boiling water reactors (BWR)--that had been in commercial operation for at least one year as of December 31 of each of the years indicated.2 Figures 1 and 2 serve to display some of this information graphically.
Figure 1 indicates that the total number of man-rems per year incurred by workers at nuclear power facilities continues to increase, while the number of reactors is leveling off.
The average number of man-rems per reactor and the average number of workers per reactor also continues to increase each year.
The average number of man-rems per megawatt year, however, appears to have leveled off at about one, and the average dose to an individual worker remains a little less than one rem.
Figure 2 displays some of this same type of information for each of the two types of light water reactors.
The cost, in terms of total man-rems and man-rems per megawatt year of generated electricity continues to be greater for the operation of BWR's than for PWR's.
The numbers of reactors, however, is still rather small, and the information reported by a few reactors where unusual conditions or problems may have occurred could 2Some of the figures shown for 1974 are different from those shown in the previous annual reports.
The new values reflect corrections made in the dates that some of the reactors began commercial operation.
TABLE 4 *
SUMMARY
OF ANNUAL EXPOSURES REPORTED BY NUCLEAR POWER FACILITIES 1973-1977 Number of Reactors Total No. of Workers Total Average Average No.
Average No.
Man-Rems Reactor Operating Number With Measurable Megawatt-Yrs.
Annual Dose of Man Rems of Workers Per Year Type Full Year of Man-Rems Exposure Generated (Rems / Person)
Per Reactor Per Reactor Megawatt-Yr.
1973 PWR 12 9,399 9.440 4,065 1.00 783 787 2.3 BWR 12 4,564 5,340 3,344 0.85 380 445 1.4 Total 24 13,963 14,780 7,409 0.94 582 616 1.9 1974 PWH 20 6,627 9,697 6,821 0.68 331 485 1.0 o
BWR 14 7,095 8,769 4,042 0.81 507 626 1.8 Total 34 13,722 18,466 10,863 0.74 404 543 1.3 1975 PWR 2G 8,268 10,884 11,983 0.76 318 419 0.7 I
BWR 18 12,611 14,607 5,786 0.86 701 812 2.2 Total 44 20,879 25.491 17,769 0.82 475 579 1.2 1976 PWR 30 13,807 17,588 13,251 0.79 460 586 1.0 BWR 23 12,626 17,859 8,312 0.71 549 776 1.5 Total 53 26,433 35,447 21,563 0.75 499 669 1.2 1977 PWR 34 13,469 20,878 16,481 0.65 396 614' O.8 BWR 23 19,042 21,388 9,103 0.89 828 930 2.1 Total 57 32,511 42,266 25,584 0.77 570 742 1.3
- The figures on this table are based on the number of nuclear power reactors that had been in.
commercial operation for at least cae year as of December 31 of each of the years indicated L
.x-..- -
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_ _ _ _ _ _ _ _ _ _ _ _ drastically affect the figures.
In an effort to identify these plants, Tables 5 and 6 list the PWR's and the BWR's in ascending order of man-rems per reactor.
For example, one can see that in 1973 the doses incurred by 3,000 workers at one of the oldest PWR's, Indian Point 1, contributed more to the total number of man-rems than did all the other PWR's combined.
This was due primarily to extensive repairs of the superheating system, and the plugging and testing of steam generator tubes.
Thus, a high dose year at one particular plant can impact the averages significantly.
In general, one can see from the listings that the plants having the lowest values of the three parameters each year are usually the newer plants.
Some of the older, smaller plants also appear near the top of the listings since they report a small number of man-rems; however, the ratio of their man-rems to the number of megawatt-years generated will be higher because of their limited power generation capacity.
When a plant reports a high number of man-rems, and a large man-rems to megawatt-year ratio as well, it usually indicates that the plant was shut down for extensive maintenance or modification work.
For PWR's, this work usually includes repair and inspection of leaking steam generator tubes, replace-ment of reactor coolant pump seals, and work on the control rod drive mechanisms.
For BWR's, it can indicate maintenance of the reactor water cleanup system, detection and repair of cracks in the core spray system
d.
TABLE 5 PRESSURIZED WATER REACTORS i
LISTED IN ASCENDING ORDER OF MAN-REMS PER REACTOR 1973 THROUGH 1977 1973 1974 1975 1976 1977 I
I I
I I
Man-Dose Man Man-Dose Man.
idan-Dese Man.
Man-Deze Man-Man-Dose Men.
Rems per Rems Rems per Rems Rems pu Rems Rems per Rems Hems per Rems per Worker per per Work er per per Worker per per Worker per per Work er per Site Name Sate (Rems 1 MW Yr.
Turke, Pomt 3 78 0 17 0 19 Praam filand 1 18 0 12 0 10 Ark ansas 1 21 0 14 0 04 Rancho Seco 58 0 19 0.22 Beam Vanev 87 0.26 0 27 Yankee Rome 99 0 74 0 78 Z on 1 56 0.18 0 13 kewaunee 4 0 27 0.07 Yankee Rowe 59 0.39 0 42 Pahades 100 0 30. 0.17 Marrie Yankee 117 0.14 0 29 Fort Calhoun 71 0 22 0 24 Prane Island 1&2 123 0 26 0.15 Calvert Chtts 1 14 0 15 0.10 Kewaunee 140 0.45 0.35
[
Sony 1 152 0.16 0 21 San Onotre 71 0.33 0.19 Zen 1&2 127 0.29 0 11 Maine Yankee 85 0.35 0 12 Prawie Island 1&2 300 0 42 0 71 Gmna 224 0 70 0.55 Pomt Beach 182 295 0 74 0.39 Three Man Island 1 73 0 56 0 11 Cock 1 116 0.29 0.14 St. Luce 152 0 34 0 25 Poict Beach 1&2 588 1 17 0 85 Haddam Neck 201 0 37 0 39 Yankee Rowe 116 0 47 0 80 Mdtstone Pomt 2 168 0.27 0 32 Troian 174 029 023 I
San Onofre 354 0 62 1 29 Yankee Rowe 205 0 84 1 85 Oconee 1,283 497 0 60 037 Pomt Beach 1&2 370 1.18 0.43 Pomt Beach 1&2 430 1 113 1.02 Robmson 2 695 0 83 1 51 Turkey Pomt 384 454 0 57 0 48 Pomt Beach 1&2 459 1.35 0 57 Prawie Island 182 447 0 55 0.62 Millstone Point 2 243 0.36 0.49 Haddam Neck 697 0 73 2.38 Oconee 1&2 517 0 61 0 79 San Onetre 292 0 69 0 75 Kewaunee 270 0 71 0 67 Mame Yankee 245 0 48 0 42 3
~
294 0 63 1.17 Zion 182 571 0 74 0 50 Arkansas 1 256 0 43 0 42 Pahsades 1133 1.16 3.95 Maine Yankee 420 0 68 0 97 Fort Calhoun Indian Pomt 1 5262 135
=
Sortv 1&2 884 0 52 1.23 Pahsades 306 0 62 1.01 Three Mile li and 1 286 0.35 0.54 Fort Calhoun 297 0.56 0 89 **
t Averages per Indian Point 1 &2 911 0 89 1.64 Mame Yankee 319 0 73 0.59 Arkansas 1 289 0 61 0 62 Cook 1 300 0 37 0 55 Reactor 783 1.00 2.31 Paksades 627 0 81 6967 Inden Poiet !"82 705 0 79 0 60 Fort Calhoun 313 0 61 1.18 Yankee Rowe 356 0.49 3 04 1
Robinson 2 672 039 1 16 Turkey Pomt 3&4 876 034 0 88 Oconee 1.2&3 1026 0 84 0 66 Ind.an Pomt 1:2&31071 037 0 87 Ginna 1225 1.39 4 82 G enna 538 038 1.47 Haddam heck 449 030 033 Three Maelstand t 360 0.32 0 58 Averages per Haddam Noch 703 0 88 1 42 Turkew Pomt 384 1184 0 72 122 Rancho Seco 391 G36 0 58 p
Reactor 331 0 68 0 97 Sev1&2 U.49 0 85 1 56 Gmna 636 0 84 2 56 Gmna 401 036 1.16 Robmson 2 1142 1.34 2.27 Pahades 696 0 93 2 01 Oconee 1,2&3 1329 0.83 0 89 Averages per Ret.mson 2 715 1 23 1 22 Rob nson 2 455 0 72 0.92 Reactor 315 0.76 0 69 San Onofre 880 0 66 2 96 Z.on 1&2 1004 128 0.78 ind en Pomt 1*&2 1950 123 7.14 Turkev Pomt 384 1036 039 1,12 Surrv 182 3165 1 15 3 41 Calvert Cnft:1 547 0 24 0.98 Averages per Haddam Nack 642 0 72 1.40 e
Reactor 460 0 79 0 99 San 0 notre 847 0.86 3,18 Surry 1&2 2307 1 24 2 13 Averages per Reactor 396 0 65 0.82
- indian Pomt I was def ueled in 1975.
IFor These Saes With More Than One Operatmg Reactor, the Nunters of Man + ems per Reactor es Otitamed by Divwfmq the Number of Man < erns Reported by the S4te by the Number of Reactors.
1 TABLE 6 BOILING WATER REACTORS l
LISTED IN ASCENDING ORDER OF MAN-REMS PER REACTOR 1973 THROUGH 1977 1973 1974 1975 1976 1977 I Man-Dese Man I
I I
Man-Dosa Man-Man-Do se Man Man.
Do se Man I Man.
Doze Man Rems pe, R-ms Rems per Rems Ras pn bass Rems per Rems Rems pe, Rerns per Werk er per pee Wor k *f put per Woiket pH pee Work er per per Work ar per Site Name S.te (Rems) MW Yr SteName S:te (Rems) MWYr S.TeName Site (Rems) MW Ye.
Sein Nome Site (Rams) MW Yr S te Name Site (Rems) MW Yr l
Vermont Yankee 85 0 34 0 38 La Lrosse 139 1 21 3 66 Peach Bottom 2&3 228 0 23 0 19 Duane Arnold 105 0 30 0 35 Coopee Station 198 0 63 0 37 l
P:tgrim 126 0 54 0 26 Vermont Yankee 216 0 61 0 71 Couger Staten 117 0 20 0 26 La Crosse 110 0 93 5 23 La Crosse 225 1 59 20 36 Mont>certo 176 0 43 0 52 Quad Citas 1&2 482 0 71 0 50 Vemont Yankee 153 0 ',4 0 36 Brown Ferev 1&2 234 0 11 0 69 Vermorit Yankee 258 0 40 0 61 l'
ta Cressa 221 1.40 9 21 Big Rock Pomt 276 0 98 6 13 Big Roth Pomt 180 0 60 5 15 Hatch 134 0 21 0 27 Duane Arnuid
?99 0 56 0 B4 Hamboldt Bay 266 1 26 5 32 Humboldt Bav 31B 1 07 7.39 la Crosse 234 1 42 7 31 Fiupattit k 202 0.34 0 41 Big Roth Pomt 334 0 72 7 59 Big Acck Point 285 1 18 5 56 M anticetto 349 0 41 1 00 Browns Feerv 1 325 0 14 2 01 Montualio 263 0 81 0 55 Mastone Pom 1 394 0 37 0 G8 Dresdra 1.2%3 939 0 70 0 81 Pr! grim 1 415 0.90 1 77 Humboldt Bev 339 1 28 7 53 Big Roth Pomt 289 0 59 9 97 Beowns Feriv 1&2 863 0 46 0 65 N.no Mite Pomt 567 1 03 1.38 Dresden 1.2.3 1662 1 04 1 90 Nme Mile Pomt 681 1 05 1 90 Brunswkk 2 326 0 26 1 10 Hatch 1 465 0 36 1 04 MMston, Pomt 1 663 0 56 2.95 Nmr M4 Po.nt 824 1 11 213 Pilgnm 1 79 8 1 69 2 59 Cooper Stat 6on 350 0 46 0 81 Quad Cites t&2 1031 1.14 1 06 5 Ovstee Creek 1236 1 58 2 91 Ovster Creek 984 1 05 2 27 Quad Cit.es 1&2 1618 1 49 1 55 Vermont Yankee 411 0 50 1 06 0.esden t.2&3 1694 0 91 1 50 Avwages per MWstone Pomt 1 1430 0 55 3 33 Ovster Creek 1140 0 94 3 05 Peach Bottom 2&3 840 0 39 0 61 Montitelio 1000 1 16 2 34 Reactor 380 0 85 1 36 Amaps pe, Diesden 1.2& 3 3423 1 48 4 83 Nme Moe Pomt 428 1 09 C 89 Peach Bottom 2&3 2031 0 12 1 94 Reactor 507 0 81 1 76 Monticello 1353 1 00 392 D*esden 1.283 1680 0 96 3 95 F airparr wk 1080 0 78 2.34 M1tiston* Pomt 1 2022 0 78 4 35 Humboldt Bay 683 1 31 29 70
%nswnk 2 1120 0 14 3 B6 Amages pet Quad Estws i&2 1651 1 35 1 74 N ne Mise Pomt 1383 1 27 3 99 R= actor 701 0 86 2 18 Ov ster Cr**h 1018 0 68 2 31 Ovsver Creek 1614 0.96 4 18 MWstone 1 1194 0 87 2 66 Humboldt Bsv 1935 1 25 Pidgnm 1 2468 2 01 9 23 P ; gram t 3142 1 67 9 91 Averages pe, A eeages per bactoe 547 0 71 1 52 Reactoe 828 0 39 21 I
l l
I For Those Snes W:th More 1%n One Ope armg bactor, tte Numbers of Mao 4 ems pee Reactor is Ot2tawad t v Dmding the Number at Mamms B ported by frie S:te by the Namber of Reactors
.=
_ and in the reactor vessel feedwater nozzles and spargers and, in older plants, extensive seismic and emergency core cooling system modifications.
More details on the activities conducted by each nuclear power facility for each year since 1973 can be found in the reports titled Nuclear Power J
Plant Operating Experience, (00E-ES-004, NUREG-0227, NUREG-0366 and NUREG-0483, to be published).
Table 7 presents the distribution of the cumulative doses (man-rems) among the major work functions of the personnel employed at power reactor facilities during the last four years.
This table is based on information submitted by nuclear reactors pursuant to Regulatory Guide 1.16.
Special 1
and routine maintenance continue to contribute approximately 70% of the total man-rems.
A breakdown of the information in Table 7 into the distributions for the PWR's and BWR's, separately, would show that, in 1977, 48% of the total man rems at BWR's was incurred during special main-tenance activities, as compared to 33% at PWR's.
This is another indica-tion of the impact that the performance of an unusually large number of non-routine operations at BWR's had on the number of man-rems that they reported.
The document NUREG-0482, Occupational Radiation Exposures
)
l at Light Water Cooled Power Reactors, which is to be published at a later date, will contain more detailed information on nuclear power reactor facilities.
TABLE 7 PERCENTAGES OF PERSONNEL DOSE BY WORK FUNCTION PERCENT OF DOSE WORK FUNCTION l
1974 1975 1976 1977 RE ACTOR OPER ATIONS 14.0%
10.8%
10.2%
10.6%
AND SURVEILL ANCE ROUTINE MAINTENANCE 45.4%
52.6%
31.0%
28.9%
IN-SE RVICE INSPECTION 2.7%
3.0%
6.0%
6.6%
SPECl AL MAINTEN ANCE 20.4%
19.0%
40.0%
41.4%
(
WASTE PROCESSING 3.5%
6.9%
5.0%
5.9%
RE F UE LING 14.0%
7.7%
7.9%
6.6%
w l
l l
- _ _ _ _ - Industrial Radiography Operations Annual occupational radiation exposure reports for CY 1977 were received from 339 companies using licensed radioactive sources for the purpose of conducting industrial radiography.
The number of workers reported as having received some measurable exposure (6,197) is nearly the same as that reported in 1976; however, the total number of man-rems decreased by about 450.
This resulted in an average dose per worker of 0.51 rems, the lowest reported in the last five years.' The 74 firms having an average dose per worker that exceeded 0.51 rems are listed in Table 8 in ascending order of average dose per worker.
Fuel Processors and Fabricators Annual occupational radiation exposure reports for CY 1977 were received from 20 facilities that had more than five kilograms of licensed special nuclear material (including plutonium, uranium-233, and uranium enriched in the isotopes 233 or 235) for use in fuel processing, fabrication, or reprocessing.
The total number of man-rems incurred by workers engaged in these activities also decreased from last year's values, with the average dose per worker at 0.25 rems, the lowest value reported in the last five years. Table 9 lists these facilities in ascending order of average annual dose oer worker, and.shows the activity codes for each license.
These may be interDreted as follows:
b TABLE 8 RADIOGRAPHY FIRMS LISTED IN ASCENDING ORDER OF AVERAGE DOSE PER WORKER No. of Workers Average Dose No. of Workers
- ' *** U"
g TW Licensee Name & Number (s)
With Measurable Per Worker Licensee Name & Number (s)
With Measurable Mme Man -rems E xposure (Rams)
E xposure (Rems)
Naval Electronics Systems Command Daniel International Corp-08 40038-16 10 5.31 0.53 39-01261 02 34 21.44 0 63 Frochling & Robertson Inc.
6%r n Testmo Laboratories Inc.
45-08890-01 11 6.OG 0.55 34 40681-03 9
5.69 0.63 X Ray Engmeering Company Associated Pipmg & Engmeering Co.
04 40616-04 257 141.47 0.55 04-02409-02 8
5.14 0.64 Astrotech Inc.
Dept. of Navy, Naval Weapons Ctr.
374992841 7
4 02 0.57 04-01757-01 9
5 90 O G6 Crane Company Midwest inspection service, Ltd.
24 00563 42 16 9 14 0 57 48-16296-01 10 6.57 0 66 El Paso Natural Gas Company Branch Radiographic Labs., Inc.
42-03201-02 4
2.29 0 57 29 43405 42 1G 10.69 0.67 Clark inspection Service Co.
Umversal Testmq Company 35-11615 41 11 6 42 0.58 43-11213 41 14 9.49 0.68 General Dynamics Corporation Arnold Greene Testing Labs, Inc.
g 06 01781 08 306 179 49 0.59 20-01074 02 26 17.86 0 69 Tulsa Gamma Ray, Inc.
Bill Miller X-Ray, Inc.
35-17178-01 8
4 72 0.59 35-15112-01 122 83.79 0 69 Superior Industrial X-Ray Co.
Nuclear Energy Serv,ce, Inc.
12-02370-01 21 12 68 0 60 42 16559 41 172 121.73 0 71 Virgmaa Dept. of Highways & Transportation Rahmond Engmeering C6., Inc.
45-13380-02 3
1.80 0 60 45 42884-01 15 10.59 0.71 Metasr *-=, Inc.
Pittsburgh Testmg Laboratory 43 17142-01 9
5 45 0 61 37-00276-25 229 163.94 0.72 R & M Weidmg & Testing Co, Inc.
H P. and Associates, Inc.
24-17183 41 1
0.62 0 62 35-16517 01 18 13.13 0 73 Charles F. Guyon, Inc.
Naval Submarme Support Facihty, New London 29-06872-02 1
0 62 0 62 06-07150-01 15 11.22 0 75 P.X. Engmeermg Company,Inc.
Industnal Inspection Industnes, !nc.
20-15102-01 2
1.24 0.62 34-14071 41 76 56.97 035 Stone & Webster Engmeermo Corp.
Thayer Inspection Service 20 45600 42 644 101.39 0 62 35-11239-01 26 19 8ti 0 76 Texas Pipe Bendmq Co. of Puerto Rico,Inc.
Quahty Assurance Lab. Inc.
52-13632-01 3
1 86 0 62 18-10634-01 4
3 09 0.77 Venegas Industrial Testmg Laborator cs, Inc.
Heat Treatmg & Metaffurgical Co.
28-14847-02 2
1.24 0 62 13-06147-04 9
7.07 0.79 Columbia Gas Transmission Corp.
Sooner X-Ray & Maq,Inc.
47-1G060 01 2
1 25 0 63 35-17259 01 3
2.37 0 79
TABLE 8 (Continued) i No of Woekers Average Dose No. of Workers Averaga Onse Lkensee Name & Number (s)
With Measurable Per Wocher Lecensee Name & Numtier(s)
With Measurable P W"' k *'
Mmm I mimsure (Hems)
Eaposure (Flems)
Consumers Power Company Calmnet Lnwneetmq Serveces 21 OH606 03 11 8.94 0 81 13-16341-01 1
1 61 1.10 91 ft. Inspection Ser ver.e Advex Corporatum 15 0620') 01 11 8 HG O 81 45-16452-01 1
1.19 1.11 Magn &Tiu m CrHjhdat6on Twm City testmg & L name.tmg L ab,Inc.
12 00672 OH
'"di 2'l4 58 0 H2 22 01316 02 72 25.31 1.15 Eastern Testmg & Inspacten. Inc.
Atlantic H* search Corporetmn 29 09014 01 11 14 3?
O 11 4 45 028011-04 4
4 81 1 22 The H C. Nuttmq Company Amerson X Hay & lent =ction. Inc.
34 14924 01 7
1 61 0 ft4 71 15455 U1 6
7.42 1.24 Comotwf eted X Hay Service Corp ingwction Sersw-Cenp ut Pa.
42O!!4560?
288 752 58 0 H3 31 11636 01 8
9 91 1.24 industeial t atmestories Inc Ca talytic, inc 41 44276 02 1
6 71 0 90 31 179314)2 6
1.52 1.25 McCochte Mav hine Shop Trans-t astern inspecten. Inc.
41 16182 01 4
3 67 0 91 31 148% o f 35 49.44 1 41 8
Yuba industries. Inc.
Combustum I ngirwenny, Inc 35-13135-01 1
6 49 0 93 35 02325 02 14 20 19 1.49 Hr.g.n t ngmeeting M Tesem Co. Inc St. L runs Testmg L ab. Inc 20 16401-01 5
4114 0 91 24 00188 02 10 14 97 1 49 X-Hay. Inc in tmtreat Gamma Inspartion 46 03414 03 45 43 15 0 91 3% 16700 01 1
1.50 1 'O Artvanced Radiation Seevere Word Instusten.s Pqpe I abreratmq 29-14111-01 5
5 10 1 07 3%1545801 6
9 22 1.54 CInvelarwi X-flay Inu*ction, Inc Tet dyne Otm> cast 35 1520401 31 34.59 1 05 34 00412 03 5
7.81 1.51 Norwt structive inspectmn Servece. Inc Newport News inrtmtrial Corporatron 41 11883 01 10 10 46 1 05 45 11589 01 5
8 05 1 61 GA., tee X Hey Servu.es, Inc Twm Porti test ng inc 3% 15194-01 45 41 15 1 06 72 15932 41 9
16 39 1.H?
Mr_ Manus inspectorsn See vn.
Colby M. T h imeier Test.rvt Co. f ac 48 14158 01 2
2.17 1 06 74 13131 01 4
1.31 1 84 Capital X. itay Service 3 G Sylvester Assocentes 35 11114 01 31 33 f,8 1 09 20 00302 02 21 41.15 196 Metits. Inc, Ii1 G,mrwil trutustrial Pepmg. Inc 42 16534 01 11 12 02 1.09 32 17316 01 1
15.12 2 25
21 TABLE 9 FUEL FABRICATORS AND PROCESSORS LISTED IN ASCENDING ORDER OF AVERAGE DOSE PER WORKER No. of Workers Average Dose Ac it With Measurable Per Worker Licensee Name & Number (s) g M
s E xposure (Rems)
Umted Nuclear Corporation SNM-777 21220 57 3.10 0.05 United Nuclear Corporation SN M-368 21230 59 3.32 0.06 1
Kerr-McGee Corporation SN M.928 21220 SNM 1174 21110 11 0.92 0.08 Nuclear Fuel Services, Inc.
SNM 124 21110 & 21S00 186 15.12 0.08 Babcock & Wilcox Inc.
SN M-42 21230 1,989 176.79 0.09 Combustion Engineering, Inc.
SN M-33 21210 34 2.95 0.09 E x xon Nuclear Company, inc.
SNM-1227 21210 & 21120 1,386 1;3 62 0.10 Te xas instruments, Inc.
SNM-23 21230 & 22120 26 3.57 0.14 U.S. Nuclear, Inc.
SN M-1315 21230 82 12.32 0.15 Babcock & Wilcox Co.
SNM 1168 21230 & 11300 124 19.44 0.16 Nuclear Materials & Equipment Corporation SN M-145 21220 39 7.55 0.19 Atomics International SNM-21 21230 & 21300 436 91.03 0.21 General Atomic Company SNM-696 21230 244 50.21 0.21 General Electric Company SNM 1097 21210 & 22110 690 155.77 0.23 Nuclear F uel Services, Inc. 2 CS F-1 43110 56 15.44 0.28 Combustion Engineering Co.
SNM-1067 21230 & 22110 128 45.99 0.36 Westmghouse Electric Corporation SNM-1120 21110 & 21120 52 24.04 0.46 Westmghouse Electric Corporation SNM-1107 21210 542 347.45 0.64 Nuclear Materials & Equipment Corporation SNM-414 21120 37-04456-03 03211 164 111.34 0.68 General Electric Company SNM-960 21120 TR 1 21300 DR 10 42140 699 504.64 0.72 I Fuel Fabrication Operations Have Ceased. Present Licensed Activity is for Storage Only.
2 Fuel Reprocessing Operations Have Ceased. Present Licensed Activity is for Possession of irradiated Material.
. - _ _ _ _ _ _ _ _ _ 21110 - Plutonium in fuel fabrication and scrap recovery 21120-Plutoniuminfuelfabrication 21210 - Uranium in UF conversion, fuel fabrication and scrap recovery 21220 - Uranium in fuel fabrication and scrap recovery 21230 - Uranium in fuel fabrication 21300 - Uranium-233 uses, other than those given above 22110 - Plutonium, unencapsulated uses 22120 - Plutonium, neutron sources 23200 - Special nuclear material, storage only 42140 - Test reactors 43110 - Fuel reprocessing plants Manufacturers and Distributors Annual occupational radiation exposure reports were received from 30 licensees that had quantities of radioactive material in excess of the values given in 10 CFR 20.407(a)(4) for purposes of processing or manu-facturing them for distribution.
The number of licensees and the number of workers receiving measurable exposures increased by about 24% over the number reported in 1976.
The total number of man-rems, however, increased by only 8%, resulting in the average dose per worker falling to 0.54 rems.
The eight companies having an average dose per worker that exceeded the 0.54 rems average are listed in Table 10 in as-cending order of average dose per worker.
TABLE 10 MANUFACTURERS AND DISTRIBUTORS LISTED IN ASCENDING ORDER OF AVERAGE DOSE PER WORKER No. of Workers
^'9' Total Licensee Name & Number (s)
With Measurable Per Worker Man-rms E xposure (Rems)
New England Nuclear Corporation 20-00320-09 16 12.43 0.78 Minnesota Mining & Manufacturing Co.
I 22-00057-06 51 49.25 0.96 d
New England Nuclear Corporation 20-11868-01 195 195.62 1.00 Mallinckrodt/ Nuclear 24-04206-01 341 385.15 1.13 Mallinckrodt. Inc.
29-13564-01 77 125.03 1.62 New England Nuclear Corporation 20-00320-13 152 274.60 1.81 Automation Industries, Inc.
37-00611-09 5
9.92 1.99 Picker Corporation 34-07225-14 6
17.18 2.86
. II.
TERMINATION REPORTS - 10 CFR 20.408 Terminations - 1969-1977 l
I During the years the repository has been in operation, approximately 245,000 reports of terminations have been received for employees of covered licensees.
These reports provide information for about 135,000 individuals.
The difference in the figures given for the number of reports and for the number of individuals indicates that several thousand of these individuals have terminated more than once over the years.
For the last few years, more than 75% of the termination reports have been for individuals that worked at nuclear power facilities.
4 Transient Workers l
Since nearly 50% of the termination reports submitted have indicated periods of employment less than 90 days, it is possible that several thousand individuals could have been employed by two or more licensees during the same quarter.
The exposures of these " transient workers" (i.e., individuals who began and terminated two or more employments with different employers within the same calendar quarter) are periodically examined to determine whether or not individual cumula-tive doses have been exceeding regulatory limits.
Table 11 shows that the number of transient workers has been increasing during the last few years.
This is due primarily to the requirement for short-term workers in the nuclear power plants.
The values of the average
s 4
lr TABLE 11 TRANSIEt1T WORKERS 1969 1970 1971 1972 1973 1974 1975 1976 1977*
Number of Workers Terminating Employ-ment with Two or 8
29 11 69 157 354 714 1311 384 Pore Employers in One Guarter Total t1 umber of t'an-rems 5.4 14.6 2.8 61.3 135.5 175.9 507.1 909.9 201.0 Average Indivi-dual Dose (Rems) 0.67 0.50 0.25 0.89 0.86 0.50 0.71 0.69 0.52 U
t i
- Data for 1977 is incomplete.
Projections of this limited data to the end of the year indicate that these figures for 1977 will be about the same as for 1976.
_ _ _ _ _ _ _ _ individual transient worker's exposure shown in Table 11 appear to be nearly the same as that given in Table 4.
This is not necessarily the case, however, since the average exposure shown in Table 11 is an average quarterly exposure for 95% of the transient workers, while the values in Table 4 indicate average annual exposures.
- However, the average exposure of these workers continues to be less than 20%
of the quarterly limit of three rems, and fewer than 10 of these individuals have ever incurred exposures that exceeded three rems in one quarter.
Career Doses The termination data also parmit estimation of accumulateo whole body dose that workers have received during their total period of employment in the nuclear industry.
This was done by summing each individual's periods of employment and each corresponding whole body dose to give the cumulative occupational dose that the individual has received during his career.
The data, however, are limited in the folloting ways:
(1) Termination information is submitted to the repository only for those individuals that are employed by the types of NRC licensees previously described on page 1.
(2) It is not always known whether the dates given in the termination reports indicate the individual's complete period of employment or just the period
- -__ _ _ _ - _ _ _ _ that he was monitored while he was assigned to work in radiation areas.
It is believed, however, that for the majority of the individuals, the two periods are identical.
(3) The exposure information is obtained from the readings of personnel monitor-ing devices used in routine monitoring programs.
The results are sufficient to characterize the radiation environment of the worker, but they may not be directly suitable for use in the assessment of risk to individuals.
We have examined the termination information currently available for the four types of covered licensees (power reactors, fuel fabricators and processors, industrial radiographers and manufacturers and distributors) for 98,846 individuals.
The periods of employment and whole body doses were summed as described above, and were broken down into ten ranges of employment periods:
0 - 90 days; 90 days -
1 year; 1 - 2 years; 3 - 4 years; 4 - 5 years; 5 - 10 years; 10 - 15 years; 15 - 20 years; and greater than 20 years.
Appendix C lists the number of individuals whose total period of employment fell within these ranges, the total number of man-rems received, and the average career dose per individual.
We have subtracted the number of these individuals who received no measurable exposure from the total number of individuals monitored to show the number of workers having measur-able doses.
Since these workers are more likely to be routinely
_ _ - - employed in radiation areas, the average doses shoe in Accendix C were calculated by dividing the total number of man-rems by the number of workers with neasurable doses.
Figure 3 shows the average career doses for workers emoloyed by the four categories of covered licensees. The average career doses for workers in the nuclear power industry continue to be higher than for workers in the other three fields.
In every. instance, however, the average dose is less than the career dose limit specified for radiation workers, 5(N-18) rems, where "N" is the individual's age in years.
FIGURE 3 CAREER DOSES 10 EsE23 U L FABRICATORS & PROCESSORS l
1 1
ANUFA TURER & DISTe BUTORS 7-E 6-2 t8 m
O
?
sj 5
a.
4 b
~
?
h
-l\\
w m
3-g j
i ll 2-m
[
e F
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L 1
3 0
0 1
1-2 2-3 3-4 4-5 5-10 10-15 15-20
>20 PERIOD OF EMPLOYMENT (YE ARS)
__. III. PERSONNEL OVEREXPOSURES - 10 CFR 20.403 and 10 CFR 20.405 Types of Overexposures One requirement of the above-referenced sections of Part 20, Title 10, Chapter 1, Code of Federal Regulations, is that all persons licensed by the NRC must submit reports of all incidents involving personnel radiation exposures that exceed certain levels.
Based on the magnitude of the expo-sure, the reports may be placed into one of three categories:
A.
10 CFR 20.403(a) - Exposure of the whole body of any individual to 25 rems or more; exposure to the skin of the whole body of any individual to 150 rems or more; or exposure of the extremities (feet, ankles, hands or forearms) of any individual to 375 rems or more.
The Commission must be notified immediately of these events.
B.
10 CFR 20.403(b) - Exposure of the whole body of any individual to 5 rems or more; exposure of the skin of the whole body of any individual to 30 rems or more; or exposure of the extremities to 75 rems or more.
The Commission must be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of these events.
C.
10 CFR 20.405 - Exposure of an individual to radiation or concentra-tions of radioactive material in excess of any applicable, quarterly limit in Part 20 or in the licensee's license.
This includes reports of whole body exposures that exceed 1.25 rems, or that exceed 3
_____ rems, as previously discussed on page 5.
It also includes reports of skin exposures that exceed 7.5 rems, extremities exposures that exceed 18.75 rems.
Reports of exposures of individuals to concen-trations in excess of the levels given in 10 CFR 20, Appendix B, usually fall into this category.
These reports must be submitted to the Commission within 30 days of the occurrence.
A short description of the four incidents occurring in 1977 that resulted in exposures of the magnitude described for category A or B is included in Appendix B of this repurt.
Summary of Overexposures Table 12 summarizes all of the personnel overexposures to external sources of radiation as reported by Commission licensees pursuant to 10 CFR 20.403 and 20.405 during each of the years 1971 through 1977.
It shows the number of individuals that incurred various types of overexposures while employed by one of several types of licensees.
Most of the overexposures included in the "All Others" category come from test reactors, universities and facilities with large irradiator sources.
The total of these figures for each of the last seven years indicates that the total number of individuals reported as having incurred overexposures to some part of the body has ranged between 46 and 66, with the exception of 1974 when 40 workers at one power reactor slightly exceeded the quarterly limit.
The 1
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In 1977 the number of individuals overexposed during industrial radiography operations, as well as the number of man-rems, decreased sharply from previous years.
The incidents involving the largest doses, however, are consistently reported by industrial radiographers and large irradiator facilities.
The number of reported personnel exposures to airborne concentrations of radioactive materials in excess of limits was considerably less in 1977 than in previous years.
This was partly due to a change in the reporting requirements.
There were only four cases in which the esti-mated intake of radioactive material exceeded the quarterly intake limit, equivalent to exposure for 520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br /> at the maximum permissible concentra-tions (MPC-hours).
None of these cases exceeded the annual intake limit, equivalent to 2000 MPC-hours.
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APPENDIX B OVEREXPOSURE SUMMARIES 1977 Industrial Radiography - License Number 20-00302-02 On June 16, 1977, a radiographer and his assistant were conducting
)
radiography operations utilizing 36 curies of cobalt-60 and 95 curies
)
of iridium-192.
After completion of the cobalt exposures, the source was properly retracted into the projector, but the source plug was not replaced and the guide tube was left attached.
The iridium projector was then set up and, after the exposure time elapsed, the assistant radiographer mistakenly cranked out the cobalt source instead of crank-ing in the iridium source.
Upon entering the vault, he claimed his survey meter did not indicate any radiation levels.
Believing the area to be safe, he proceeded to remove the exposed film.
The radiographer then entered the vault to set up the next shot, and he claimed his survey meter was reading zero.
It was only after completion of this set up and leaving the vault to crank out the iridium source, that the mistake was discovered.
The radiographers immediately cranked in both sources and called their supervisor who sent their badges for emergency processing.
From film badges worn by the two individuals and re-enactments of the incident, it is estimated that the radiographer received a dose of 4 rems to the trunk of the body, up to 11 rems to the gonads, up to 18 rems to
_ _ _ _ _ _ _ the eyes, and from 100 to 400 rems to two small areas on the left side of the head where he bumped it on the iridium guide tube.
It is estimated that the assistant radiographer received a whole body exposure of 4 rems.
Corrective actions included a refresher course for all radiographic per-sonnel in the operation of survey meters and proper methods of conducting radiographic surveys.
See also NUREG-0090-08, " Report to Congress on Abnormal Occurrences, April - June 1977."
Industrial Radiography - License Number 06-01781-08 On September 7, 1977, while conducting industrial radiography on a sub-marine under construction in the Shipyard, a reel operator (a qualified radiographer) was exposed to radiation from 80 curies of iridium-192 for approximately 2-1/2 minutes.
After completion of the radiograph, the reel operator cranked in the source and proceeded to set up for the next exposure while the head radiographer was gone.
Evidently the operator failed to fully retract and lock the source.
He also failed to follow proper procedures by not waiting for the responsible radio-
)
grapher to return, and by neglecting to determine the radiation levels h
in his work area.
The dose estimate for the reel operator was determined to be 5.2 rems to the whole body and 18 rems to the right foot.
All radiographers have been re-instructed in the importance of compliance with written procedures, especially in the use of survey meters.
The present training programs are being reviewed to determine if more strin-gent standards are necessary to prevent a recurrence of this type of l
l 4
- incident.
The reel operator was disciplined for failure to comply with operating instructions.
l Industrial Radiography - License Number 37-02607-02 On November 12, 1977, a radiographer was conducting radiography operations using a 75 curie iridium-192 source.
Af ter making several exposures, the radiographer attempted to return the source to its shielded position when he noticed that his survey meter was still reading 125 millirems per hour.
This reading was the same as when the meter was sitting on top of the storage container.
Realizing the source was still in the collimator, he proceeded to adjust the collinator with his hand in order to retract the source back into the container.
He then called his supervisor to report the incident.
Af ter several re-enactments of the incident, using dosi-meters in critical areas, it was determined that the radiographer received a whole body dose of approximately 1 rem and from 300 to 600 rems to the first two fingers of the lef t hand.
The radiographer's hand was calcu-lated to have been in close proximity to the source for approximately 3 to 5 seconds.
As a result of this incident, the licensee has initiated a new formal management audit system to augment their present program of f
internal audits.
The licensee also plans to retrain each radiographer and to confirm his level of comprehension with written tests and observation of on-the-job activities.
See also NUREG-0090-10, " Report to Congress on Abnormal Occurrences, October - December 1977."
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _. _ _ Irradiator Facility - License Number 29-13613-02 On September 23, 1977, a worker entered an irradiator facility while an array of sealed sources containing 500,000 curies of cobalt-60 was exposed.
The normally electrically interlocked access door was dis-connected, and the worker had not been told that the source array was in the exposed position.
The individual stood about 10 feet from the source for a period of 10 seconds, which resulted in a dose to the whole body of approximately 220 rems.
He was hospitalized for medical observation and treatment.
The incident was directly caused by the decision of management to allow the source to be raised with the inter-lock and safety devices inoperative.
Operation of the in-air irradiator when interlocks are inoperative is not only a violation of internal operating procedures, but also a violation of license requirements.
Contributing factors included failure to conduct surveys and failure to follow procedures to control access to high radiation areas.
See also NUREG-0090-10, " Report to Congress on Abnormal Occurrences, October -
December 1977."
A
- 44 APPENDIX C CAREER DOSES FOR RADIATION WORKERS TERMINATING DURING THE YEARS 1969 1977 NUCLEAR POWER REACTORS Number of Number of Total Average Dose (rems)
Total Length of Monitored Individuals Number for the Period Employment Individuals with Measurable Doses of Man rems of Employment 0 90 Days 43,668 26,047 16,653 0.64 90 Days - 1 yr.
18,663 13,363 14,209 1.06 12 yrs.
4,217 3,270 5,388 1.65 2 3 yrs.
1,510 1,197 2,862 2.39 3-4 yrs.
692 600 1,678 2.80 45 yrs.
269 221 900 4.07 5-10 yrs.
431 386 1,898 4.92 10-15 yrs.
131 113 669 5.92 15-20 yrs.
36 33 265 8.03
> 20 yrs.
54 45 237 6.41 INDUSTRI AL RADIOGR APHERS 0-90 Days 2,408 1,680 743 0.44 90 Days - 1 yr.
3,597 2,760 2,310 0.84 1-2 yrs.
2,546 1,935 2,802 1.45 2 3 yrs.
1,660 1,309 2,424 1.85 3-4 yrs.
1,158 927 2,039 2.20 4-5 yrs.
910 760 2,133 2.81 5-10 yrs.
2,968 2,587 9,285 3.59 10-15 yrs.
2,105 1,891 8,831 4.67 l
15 20 yrs.
787 720 3,442 4.78
> 20 yrs.
3,281 2,662 7,992 3.00 I
FUEL FABRICATORS AND PROCESSORS 0 90 Days 2,111 1,307 554 0.42 90 Days - 1 yr.
1,614 1,313 690 0.53 l
12 yrs.
1,020 944 974 1.03 2 3 yrs.
566 536 787 1.47 3-4 yrs.
408 390 535 1.37
{
4-5 yrs.
235 225 341 1.52 5-10 yrs.
710 677 1,891 2.79
(
10-15 yrs.
314 29 6 1,231 4.16 15-20 yrs.
135 126 496 3.94
> 20 yrs.
72 69 411 5.96 MANUFACTURERS AND DISTRIBUTORS 0-90 Days 103 77 21 0.27 90 Days.1 yr.
161 132 86 0.65 12 yrs.
113 97 107 1.10 2-3 yrs.
70 59 74 1.25 3-4 yrs.
28 17 37 2.18 4 5 yrs.
13 12 42 3.50 5-10 yrs.
55 55 230 4.18 10-15 yrs.
19 19 73 3.84 15 20 yrs.
8 8
38 4.75
> 20 yn.
0 0
0 0
"#"~"
U S. NUCL E AR REGUL ATORY COMMISSION I) 771 BIBLIOGR APHIC DAT A SHEET NUREG-0463 4 1LT L E AN D SUUTiT LE (A dd Volume Ivo, af anoropnatel 2 IL er e tw k )
TENTH ANNUAL OCCUPATIONAL RADIATION EXPOSURE REPORT,1977 3 ne c,,t y r s,cce ss,gy yg
/ AU T HO H 4Si
' U A r t at Paa l COMPT t IE L
[. i.m wmn Barbara G. Brooks September 1978 9 Pt M OH MIN G O HGANIZ A TION N AME AND M AILING ADD RE SS Hoc /adr I,;> C de/
D AT E RE POH T ISdut D dc"Mer Il0f8 U.S. Nuclear Regulatory Commission Office of Management and Program Analysis
- > 't"""
Washington, D.C.
20555 b il c w' Nan k i 12 SPONSOHIN G OHG ANi2 ATION N AVE AND M AILING ADDHE SS uric'sde 2 0 Codel 10 PROJE C T. T Abe, TiOHF uni i N U U.S. Nuclear Regulatory Commission Office of Management and Program Analysis n CONTHActNo Washington, D.C.
20555 13 TY PE OF REPORT PE RiOO COV E HE D //nclusive dares t Annual Calendar Year 1977 15 SUPPLEME N T A H) N OTE S 14 (L eave h/a"* /
16 ABS TH ACT (200 words or less/
This is a report which summarizes the information reported by certain NRC licensees to the Commission's centralized repository of personnel occupational radiation exposure information.
The bulk of the information in the report is derived from annual and termination reports submitted by commercial nuclear power reactors, industrial radiographers, fuel fabricators and processors and commercial distributors of byproduct materials in accordance with the require-ments of 10 CFR 20.407 and 20.408.
E
\\
17 K E Y WOR DS AND DOCUME N T AN ALYSIS 17a DE SC hip T O H5 Not Applicable.
17t, IDE N TI F IE HS' OPE N E N DE D TE RMS
21 NO 06 F Auf Not Applicable.
Unlimited.
20 st CuHi T Y ct, Ass trh,s v,</
22 PHice Not Applicable, s
N AC F ORM 33$ (7 7 7)
_ _. _ _ _ _ _ _. _ _ _ _ _ _