ML19318B546

Ninth Annual Occupational Radiation Exposure Rept,1976

ML19318B546
Person / Time
Issue date:	10/31/1977
From:	NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA)
To:
References
NUREG-0322, NUREG-322, NUDOCS 8006270026
Download: ML19318B546 (42)

Text

. -. _

NUREG-0322 NINTH ANNUAL OCCUPATIONAL RADIATION EXPOSURE REPORT,1976 I

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Office of Management Information and Program Control

'.U. S. Nuclear Regulatory Commission 8006270026

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Available from National Technical Information Service 1

Springfield, Virginia 22161 Price: Printed Copy $4.50; Microfiche $3.00 The price of this document for requesters outside of the North American Continent can be obtained from the National Technical Information Service.

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1 QUESTIONNAIRE I

I These annual reports of occupational radiation exposure have been distributed l

free of charge to all utility, architect / engineer and reactor manufacturing l

companies and many other interested parties for several years. We would now g

like the readers to assist us in evaluating this publication by completing this questionnaire.

I When properly folded, the reverse of this page forms a pre-addressed franked l

envelope. After completing the questionnaire, fold and staple or tape the l

page such that the address is on the outside. We would appreciate your y

returning the questionnaire by January 15, 1978.

I I find the publication ANNUAL OCCUPATIONAL RADIATION EXPOSURE REPORT to be:

I useful for some specific applications.

l of no specific use, but interesting to read.

g not useful to me in any manner.

If you do not want future issues, please indicate your company's name l

In regard to presentation of exposures being experienced by certain types l

of NRC licensees, I find that this publication:

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provides a good spectrum of information.

is not as complete or timely as other publications.

IM contains no information that I do not already receive.

le lr In regard to the clarity of the material contained in this publication, I l8 find it is:

I presented in a clear, logical fashion that is easily understood.

I presented in a fashion that is more confusing than enlightening.

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I find this publication to be:

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biased.

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FOLD HERE e-__________________-_________________c F

7 UNITED ST ATES NUCLE AR REGU L ATOF4 / COMMISSION POST AGE AND FEES PARD W ASHING TON. D. C. 20555 U.S. NUC LE A R R EGU LA TOR Y C O M MISSIO N OF FICI AL BUSINESS PE N ALTY F OR PRit.' AT E USE. $3OO k

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 ATTN: Barbara Brooks 11600 MNBB FOLD HERE

NUREG-0322 NINTH ANNUAL OCCUPATIONAL RADIATION EXPOSURE REPORT,1976 1

Manuscript Completed: October 1977 Date Published: October 1977 Division of Operations Evaluation Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555

M TABLE OF CONTENTS Page Summary.....................................................

iii Preface.....................................................

1 I.

ANNUAL REPORTS Exposure Distributions................................

3 Man-Rems Per License Type.............................

5 Commercial Nuclear Power Facilities...................

7 II. TERMINATIONS Terminations, 1976...................................

12 Terminations, 19 69-197 6..............................

12 Transient Workers, 1969-1976.........................

12 III. PERSONNEL OVEREXPOSURES Types of 0verexpos u res...............................

15 Summa ry o f 0ve rexposures.............................

16 TABLES 1.

Distribution of-Annual Whole Body Exposures Reported by Covered Licensees, 1976.................................

4 2.

Summary of Annual Whole Body Exposures for Covered Licensees,- 1968-1976....................................

6 3.

Man-Rems Accumulated by Category of Covered Licensees, 1973-1976...............................................

8 4.

Summary of Annual Exposures Reported by Nuclear Power Facilities, 1974-1976..................................

10 5.

Percentage of Personnel Dose by Work Func' tion..........

11 6.

. Transient Workers, 1969-1976...........................

14 7.

Summary of Overexposures to External Sources of Radiation..............................................

17 APPENDIX A - Licensed Nuclear Power Facilities Annual-Whole Body Exposures, 1974-1976.....................

19 APPENDIX B - Overexposure Summaries........................

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SUtiftARY This is a report by the U.S. Nuclear Regulatory Commission on the operation of the Commission's centralized repository of personnel occupational radiation exposure information.

The report is published

{

annually and is available at all NRC public document rooms or may

= be purchased from the National Technical Information Service in 5pringfield, Virginia.

The bulk of.the information summarized in the report was obtained from annual and termination reports submitted _by certain types of NRC licensees (i.e., operating nuclear power reactors; industrial

.radiographers; fuel fabricators and processors; and commercial processcrs and distributors of specified quantities of byproduct 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, respectively.

' Annual reports were received from 430 covered licensees which indicated

'that some 92,773 individuals, each with an average annual exposure of 0.36 rems, were monitored during.1976. Termination reports received ifrom these: licensees: indicated that 32,400 individuals terminated their employment 1or work assignment with them in 1976.

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Information on incidents involving personnel overexposures to radiation or radioactive materials is obtained from reports submitted by all flRC licensees purst. ant to Parts 20.403 and 20.405 of Title 10, Chapter 1, Code of Federal Regulations. The number of overexposures reported ir 1976 showed an increase over the number reported in 1975 but it is about the same as those reported in previous years.

The more significant overexposures which occurred in 1976 are summarized.

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illflTH ANNUAL OCCUPATIONAL RADIATION EXPOSURE REPORT 1976 PREFACE On November 4,1968, the U.S. Atomic Energy Cornission (AEC) approved a program for the reporting of certain occupational radiation exposure information to a central repository.

This information was to be l

required of four categories of AEC licensees, ar 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 sumnarized this information and were published as six separate documents (WASH-1350-R1 through WASH-1350-R6).

With the division of the AEC into the two agencies, the Energy Research and Development Administration (ERDA) and the U.S. Nuclear Regulatory Commission (NRC), in January 1975, each agency assumed responsibility for collecting and maintaining occupational exposure information reported 10perating nuclear power reactors; industrial radiographers, fuel processors, fabricators and reprocessors; commercial processors and distributors of specified quantities of byproduct material.

1

by_ facilities under.their respective jurisdictions. Beginning with the annual report for calendar year 1974,2 the NRC's publication no longer contains information pertairjing to ERDA facilities or contractors.

Comparable information for ERDA facilities and contractors is collected by ERDA's Division of Safety, Standards and Compliance at Germantown, Maryland.

2The annual occupational. radiation exposure reports for NRC licensees for 1974 and 1975 are available from NTIS as NUREG 75/108 and NUREG-0119, respectively.

The annual radiation exposure reports for ERDA contractors for -1974 and 1975 are available' from NTIS as ERDA-76/119 and ~ ERDA-77-29,

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respectively.

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ANNUAL REPORTS - 10 CFR 20.407 i

Exposure Distributions e

On February 4, 1974, 10 CFR 20.407 was amended to require the four categories =of covered licensees to submit an annual statistical report which' indicates the distribution of the whole body exposuresl incurred by their employees.

Table 1 is a compilation of the reports i

submitted for calendar year 1976. As can be determined from the data presented in'this table, 46% of the 92,773. individuals monitored during 1976 received exposures that were too small to be detected by personnel radiation monitoring devices and 99.6% of the exposures were less than-5 rems.

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It should be pointed out that very few of the-annual exposures that -

exceed 5 rems are personnel overexposures. 'Although 5 rems is-the i;

annual limit set forth in Paragraph (a) of 10 CFR 20.101, Paragraph r

(b) ' permits licensees, under certain conditions, to allow a worker.

j to receive 'a whole body dose of-3 rems per calendar quarter (or 12 b

lAll'of the1 figures compiled in this report relating.to exposures and/or. doses are based on the results and interpretations of the -

readings of various typestof personnel monitoring devices-employed-by each licensee.

This information obtained from routine personnel L monitoring -programs is' not directly suitable for interpretation as:

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< dose ~ equivalent to the individuals involved, but is sufficient to characterize the radiation environment.in:which individuals work and may be.used Lin: evaluating the radiation protection program.

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TABLE 1 DISTRIBUTION OF ANNUAL WHOLE BODY EXPOSURES BY LICENSEE CATEGORY 1976 Covered,.

Exposure Ranges (Rems)

Categories 0.25-.0.50-0.75-of NRC' Total No'.

Less Than Measurable 0.10-Licensees Monitored Measurable

< 0.10 0.25 0.50 0.75 1.00 1-2 2-3 3-4 4-5L5-6 6-7 7-8.8-9 9-10' 10-11 11-12

>12

. POWER.

-REAClORS

.30.085 13,859 5,277 4,192 2,537 2,036 4,882 2,355 789 487 188. 70 26 11 5

1.

0 0

No. of Indiv.

66,800 Percent of Total -100%'

~45%

21%

8%

6%

4%

3%

7%

4%

1% :l%

INDUSTRIAL RADIDGRAPHY No. of Indiv.

11.245

.5,023 2,184 1,208 887 544 353 660 210 100 41 15 1) 3 2

0 2

0 3'

4, Percent of Total 100%

45%

19%

11%

8%

5%

3%

6%

2%

1%

FUEL PROCESSING'

& FABRICATION

.No. of Indiv.

11,227 5,942 2,815 959 580 307 221 237 77 47 25 17 0

0 0

0 0

0 0'

Parcent of Total 100%

53%

25%

9%

5%

3%

2%

2%

1%

MANUFACTURING &

DISTRIBUTION No. of Indiv..

'3,501 1,525 906 413 170 94 53 148 77 51 31 16 10 5

2 0

0 0

0, Percent of Total 1001 44%

26%

12%

5%

3%

2%

4%

2%

1%

1%

TOTALS Number 92,773 42.575 19,764 7,857-5,829 3,482 2,663 5,927 2,719 987 584 236 90 34 15 5

3 0

3 Parcent-100%

46%

21%

8%

6Y 4%

3%

6%

3%

1%

1%

t remsannually).

The conditions are that (1) the licensee must have determined and recorded the worker's 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. Annual exposures that exceed 12 rems indicate that an overexposure has occurred; however, not all overexposures must exceed 12 rems in order for them to be reported. A discussion of various types of overexposures that have occurred is given in Section III.

4 A summary of the annual whole body exposures reported to the repository during the past eight years is presented in Table 2.

One can see that about 95% of the exposures have consistently remained less than 2 rems and that the number of individuals receiving an annual exposure in excess of five rems is about one half of one i

percent of the total number of individuals monitored each year.

l Man-Rems per License Type The statistical data contained in the annual reports required by 1

10 CFR 20.407 permit an estimate to be made of the number of man-rems accumulated by the four covered categories.

This was done by taking each licensee's annual report and summing the products obtained by multiplying the numbers of individuals in each of the exposure ranges (shown in Table 1) by the midpoint exposure of each range.

These 5

TABLE 2

SUMMARY

OF ANNUAL WHOLE BODY EXPOSURES

'FOR COVERED LICENSEES 1968-1976 Percent of Percent of Number of' Total Number Exposures Exposures Annual Exposures Year honitored

< 2 Rems 55 Rems

> l2 Rems 1968

-36,836 97.2%

0.5%

3' 1969 31,176 96.5%

0.5%

.7 1970 36,164

-96.i%

0.6%

0 m

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%

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numbers developed for each ~1icensee in the four categories were then totaled't'o yield the information shown in Table 3.

Also shown 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 t

were obtained by dividing the same total number of man-rems by the number of those individuals reported as having received a measurable exposure.

The latter average was calculated for radiation workers because it deletes the minimal exposures of many individuals who are monitored for convenience or for identification purposes.

In 1976 the average exposure for workers employed by licensees in all four categories decreased slightly from last year's values as did the overall i

average. The averages consistently remain less than one rem.

Commercial Power Reactor Facilities More than 70 percent of the individuals annually reported as being monitored during the last three years have been employed at nuclear power facilities. Appendix A has been added to this report to present the annual exposure data that has been submitted by each nuclear power plant during the past three years. All of the plants presented were in commercial operation as of December 31, 1976. The values-in the last two columns indicate the total man-rems per site and the average individual exposure. These values were calculated as described in the 7

7" TABLE 3 MAN-REMS ACCUMULATED BY CATEGORY OF COVERED LICENSEES Covered Average Exposure Average Exposure Categories-

. Calendar Licensees Individuals With Measurable Total No.

Individual (Based Individual (Based on Number of

- Total No.

No,' Individuals (Rems) Per (Rems) Per of NRC Licensees Year Reporting Monitored Exposure Man-Rems on Total Monitored)

Measurable Exposures).

Commercial 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' 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 co Fuel Processing and Fabrication 1976 21 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 Distribution 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 1976 428 92,773 50,198 33,240 0.36 0.66 Overall 1975 387 78,713 40,081 28,379 0.36 0.71 Averages 1974 421

~85,097 33,291 20,810 0.24 0.63 1973 443 67,862 28,867 21,268 0.31 0.74

above section " Man-Rems per Category." Table 4 summarizes this annual exposure data by reactor type, pressurized water reactor (PWR) and boiling water reactor (BWR) for those reactors that had been in commercial operation for at least one year as of December 31 of each of the years indicated.

It appears that the requirements, in terms of man-rems and workers per reactor, continue to be greater for the operation of BWRs than for PWRs.

However, the values of the average number of man-rems and average number of workers per reactor for BWRs in 1976 decreased somewhat from the 1975 values while those for PWRs increased.

Table 5 presents the distribution of the cumulative doses (man-rems) among the major work functions of the workers at power reactor fac'lities J

during the last three years.

This table is based on information submittec by nuclear reactors pursuant to Regulat6ry Guide 1.16.

In 1975 enly about half of the facilities submitted the information in a format ac,uate to categorize the exposure by work function.

In 1976 more than.three fourths of the facilities submitted this information properly and it was found that special and routine maintenance continue to contribute approximately 70% of the total man-rems.

The document NUREG-0323, " Occupational Radiation Exposures 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.

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TABLE 4

SUMMARY

OF ANNUAL EXPOSURES REPORTED BY NUCLEAR POWER FACILITIES 1974-1976 Number No. of Workers Total Avera9e Average No.

Average No.

Reactor Operating With tieasurable Number Exposure of Man-Rems of Workers Year Type Full Year Exposures of Man-Rems Rems / Person Per Reactor Per Reactor 1974 PWR 18 9,370 6,556 0.70 364 521 BWR 14 8,769 7,095 0.81 507 626 Totals 32 18,139 13,651 0.75 427 56/

25 1975 PWR 26 10,884 8,267 0.76 318 420 EWR 18 14,607 12,611 0.86 701 812 Totals 44 25,491 20,876 0.82 475 580 1976 PWR 30 17,585 13,808 0.78 460 586 BWR 23 17,859 12,626 0.71 549 776 Totals 53 35,447 26,434 0.75 499 669 The figures on this table are based on the numlier of nuclear power reactors that had been in commercial operation for at least one year as of December 31 of each of the years indicated.

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-TABLE 5 PERCENTAGES OF PERSONNEL ~ DOSE i

BY WORK FUNCTION Percent of Dose

. Work' Function.

1974 1975 1976 Reactor Operations and Surveillance 14.0%

10.8%

10.4%

Routi'e Maintenance 45.4%

52.5%'

31.7%

n In-Service Inspection 2.7%

2.9%

5.7%

Special Maintenance 20.4%

19.0%

39.5%

Waste Processing 3.5%

6.9%

4.8%

Refueling 14.0%

7.7%

7.9%

II. TERMINATIONS - 10 CFR 20.406 4

i Terminations - 1976 During 1976 some 46,604 reports of-termination of employment or j

work assignment at covered licensed facilities were received which provided personal identification, employment and exposure information.

on a total of 32,377 individuals. Both figures reflect an increase of about 20% over those reported in 1975.

The difference in the figures _given for the number of reports and for the number of individuals indicates that about 14,200 reports were received for individuals who terminated employment more than once during the year.

Terminations - 1969-1976 During the years that the_ repository has been in operation, some 166,000 reports of terminations have been received from covered

' licensees. These reports provided information for approximately 103,000. individuals. Again the difference in the two figures' indicates i

that several thousand individuals have terminated more than once over the years. 'More than 50% of the termination reports continue

.to be for individuals working at nuclear power facilities.

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Transient Workers-Since nearly 50%' of > the individuals for whom termination reports have' been' submitted indicated periods of employment less than 90 days 12

it would be possible for several thousand individuals to be employed by two or more licensees during one 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 they are excessive. Table 6 demonstrates that the number of these workers continues to increase every year, primarily because of the requirement for short-tern workers in the nuclear power plants.

The values of the average individual transient workers exposure may appear to be nearly the same as that given in Table 4.

It should be pointed out that this is not necessarily so because the average exposure shown in Table 6 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 continue to be less than 20% of the quarterly limit of three rems and fewer than 10 of these a

l individuals have ever incurred exposures that exceeded 3 rems in one quarter.

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TABLE 6 c

TRANSIENT WORKERS 1969-1976 1969 1970 1971 1972 1973 1974 1975 1976 Number.of Workers Terminating Employ-ment with Two or 8

29 11 69 157 354 714 1055 More Employers in

.0ne Quarter

- 30 5.4 14.6 2.8 61.3 135.5 175.9 507.1 745.3 n Re Average Indivi-dual Exposure-0.67 0.50 0.25 0.89 0.86 0.50 0.71 0.71 (Rems)

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III.

PERSONNEL OVEREXPOSURES - 10 CFR 20.403 and 10 CFR 20.405 Types of Overexposures

-One of the requirements of the above-referenced sections of Part 20, Title.10, Chapter 1, Code of Federal Regulations, is that all facilities or individuals having radioactive materiai licensed by the NRC must submit reports of all incidents involving personnel exposures to radiation that exceed certain levels.

Based on the magnitude of the exposure, 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 i

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 concen-trations of radioactive material in excess of any applicable 15

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quarterly limit in Part 20 or in the licensee's license.

This includes reports of exposures of the whole body that exceed 1.25 rems, or that exceed 3 rems, as previously discussed on page 3.

It also includes exposures of the skin of the whole body that exceed 7.5 rems and exposures of the extremities that exceed 18.75 rems.

Reports of exposures of individuals to concentrations in excess of the levels given in 10 CFR 20, Appendix B, usually fall into this category.

These reports must be submitted to the 4

Commission within 30 days of the occurrence.

Summary of Overexposures Table 7 summarizes the personnel overexposures to external sources of radiation reported by Commission licensees pursuant to 10 CFR 20.403 and 20.405 during 1976..The figures in the column " Number Reported" indicate the number of individuals overexposed and the figures to the right indicate the sum of the exposures received by these individuals in the overexposure incidents. Also shown are the sums of the exposures for four individuals who incurred simultaneous whole body and extremity overexposures while practicing industrial radiography.

The total of these figures indicate that during 1976 a total of 61 individuals were reported as having incurred exposures to some part of the body that exceeded applicable limits. This is 16

TABLE 7

SUMMARY

OF OVEREXPOSURES TO EXTERNAL SOURCES OF RADIATION 1976 Whole Body Overexposures Extremity Overexposures Type of Licensee Number Total of Number Total of Reported Doses (Rems)

Reported Doses (Rems)

Industrial 20 2

Radiography 115.1 860

-Power 74.3

~~

20 0

0 Reactors Manufacturing 0

0 3

71 l

Distribution Medical 6

9.9 0

0 Other 7

15.8 o

o Totals 53 2]51 5_

931 Simultaneous Whole Body and Extremity Overexposures Industrial 4

54.3 to W. Body Radiography 6943 to Extremity) t i

!This includes 3700' rems resulting from an incident-in which an exposure of 400 to 3700 rems was estimated to have been received'by the hands.

See the second incident on page 30.

17'

a considerable increase over the 39 individuals reported in 1975, but is about the same number as reported in previous years.

The number of personnel exposures to excessive airborne concentrations of radioactive materials reported during 1976 was about the same as that reported during previous years. There were only five exposures that exceeded the 520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br /> per quarter that a worker may be permitted to spend in an atmosphere containing the maximum permissible con-centration of material and all of these were less than the 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> per year that a worker may spend in such an atmosphere.

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APPENDIX A LICENSED MUCLEAR POWER FACILITIE5 ANNUAL WHOLE BODV EXPOSURES 1974, 1975, 1976 Number Average humber of Individuals with Whole Body Exposures in the following Ranges (Rems)

Total with Total Individual PLANT NAME ANO Veer T No Meas-Number Meas. Man-rems Exposure-Rees LICENSE NUMBER Measura ble urable 0.10-0.25-0.50-0.75-1.0 2.u-3.0-4.0-5.0-6.0-7.0-8.0 9.0- Mont-wrable Per Year (Measurable Esposure

<0.10 a.25 0.50 0.75 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 tored Esposure Per Site Esposures Only)

ARKANSA5 1 DPR-51 1975 488 87 44 8

5 3

635 147 21 0.14 Commercial in 8/74 1976 197 174 94 72 29 24 49 14 7

8 4

1 673 476 289 0.61 Type - PWR; 850 MWe BEAVER VALLEY 1976 1.004 99 10 2

1.115 111 7

0.07 Comercial in 6/76 Type - PWR; 852 MWe BIG ROCK POINT 1974 20 93 52 22 17 11 43 17 8

6 6

6 301 281 276 0.98 OPR-6 Commerical in 3/63 1975 34 137 60 26 12 7

23 24 6

4 1

334 300 180 0.60 Type - BWR 72 MWe 1976 15 205 90 50 33 23 41 27 12 6

1 503 488 289 0.59 BROWN 5 FERRY 182 1975 2.085 1.638 457 180 57 20 28 4.465 2,380 325 0.14 DPR-33, 52 Commercial in 8/74. 1976 2.039 1.141 285 115 37 20 9

4.246 2.207 234 0.11 3/75 Type - BWR; 821 MWe BRUh5 WICK 2 DPR-62 1976 1.816 714 203 181 65 31 49 13 3

3.081 1.265 326 0.26 Commercial in 11/75 Type - BWR 821 MWe

APPENDIX A LICENSED NUCLEAR POWER FACILITIES ANNUAL WHOLE 800Y EXPO 5URES 1974,1975,1976 (Continued)

Number of Individuals with Whole Body Exposures in the following Ranges (Rems) 8' Total Total In dual PLANT MAME AND Year No Meas.

Namber Meas. Man-rems Fxposure-Rems LICENSE NUMBER Measurable urable 0.10-0.25-0.50-0.75-

1. 0-2.0-

3. 0-

4. D-5.0-6.0 7.0 8.0-9.0. Mont-urable Per-Veer (Measurable Esposure < 0.10 0.25 0.50 0.75 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 toced Exposure Per Site Ex posures Only)

CALVERT CLIFF 5 1 1975 570 670 41 43 22 6

1 1.353 783 77 0.10 DPR-62 Commercial in 5/75 1976 1.822 360 66 45 22 11 3

2.329 507 74 0.15 Type - PWR; Both 1065 MWe D.C. COOK DPR-58 1975 590 100 32 23 7

5 3

760 170 32 0.19 hJCommercial in 8/75 1976 977 164 93 67 35 17 18 1

1.372 395 116 0.29 OType - PWR; 1090 MWe COOPER STATION 1974 667 2 32 49 35 19 5

7 1.014 347 60 0.17 DPR-46 Commercial 7/74 1975 407 404 73 40 23 12 23 4

986 579 117 0.20 Type - BWR; 778 MWe 1976 757 352 100 76 61 55 101 16 1

0 1

1.520 763 350 0.46 DRE5 DEN 1. 2. 3 1974 1.793 505 237 178 101 75 182 124 94 65 23 6

4 3.387 1.594 1.662 1.04 DPR-2, 19. ?5 Commercial in 7/60. 1975 1.687 403 210 156 125 153 629 306 166 109 29 2'

3.997 2.310 3.423 1.48 11/71. 6/72 Type - BWR; 197 1976 1.370 461 293 231 137 81 213 181 94 45 7

2 1

3.116 1.746 1.680 0.96 772, 773 MWe

APPENDIX A LICENSED huCLEAR POWER FACILITIE5 ANNUAL WHOLE BODY EXPO 5URES 197f,1975.1976 (Continued)

Number Average Number of Individuals with Whole Body Esposures in the following Ranges (Rems)

Total with Intal Individual PLANT NAME AND Year No Meas-

~

~

~ ~ ~'~~-'

~ ~ - ~

~ f4 umber Meas. Ma n-ress E s posu re-Rees LICENSE NUMBER Measura bl e urable 0.10-0.25-0.50-0.75-1.0-2.0-3.0-4.0-5.0-6.0-7.0-8.0-9.0 Mont-urable Per Year (Measurable Ex posure 0.10 0.25 0.50 0.75 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 tored Esposure Per Site Esposures Only DUANE ARNOLO DPR-491975 1,409 105 75 24 8

6 5

1,632 22?

45 0.03 Comercial in 2/75 1976 725 148 77 55 35 17 18 1,075 350 105 0.30 Type - BWR; 538 MWe FIT 2 PATRICK DPR-59 1975 754 167 74 29 17 9

9 1,059 305 64 0.21 Cammercial in 2/75 1976 705 262 152 84 3~

18 42 5

1 2

1,305 600 202 0.34 Type - BWR; 457 MWe n

FORT CALHOUN DFR-401974 232 184 68 39 15 10 10 1

559 327 71 0.22 Commercial in 6/74 1975 153 192 63 54 26 20 73 34 7

62?

469 294 0.63 Type - PWR; 457 MWe 1976 130 '

261 40 47 44 21 59 20 17 7

646 516 31 3 0.61 GINNA DPR-18 1974 98 123 65 73 57 56 262 186 48 9

4 1

982 884 1,225 1.39 Commercial in 7/70 1975 151 127 53 93 64 74 206 20 4

836 685 533 0.78 Type - PWR; 490 MWe 111 139 113 92 72 56 240 41 4

1 869 753 636 0.84 HADDAM NECK OPR-61 1974 21 5 303 85 61 28 21 30 14 5

2 1

765 550 201 0.37 Comercial in 1/68 1975 370 181 91 90 87 54 193 93 6

1,165 795 703 0.88 Type - PWRi 575 MWe 1976 356 280 58 47 35 34 12?

65 3

1,000 644 449 0.70

APPE%0!X.

LICENSED NUCLEAR POWER LITIES ANNUAL WHOLE BODY Ek RES 1974,1975.1976 (Ct.inued)

NJmber of Individuals with Whole Body Exposures in the Following Ranges (Rems)

Total h Total I

d al PLANT NAME AND Year ~

No Meas.

Number Mess-Man-rems Exposure-Rems LICENSE NUMBER Measurable urable 0.10-0.25-0.50-0.75-1.0-2.0-3.0-4.0-5.0-6.0-7.0-8.0-9.0- %nt-urable Per Year (Nasurable Ex posure 0.10 0.25 0.50 0.75 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 tored Exposure Per Site Exposures Onir)

E.1. HATCH DPR-57 1975 477 231 88 37 25 11 9

1 1

1 851 374 90 0.24 Commercial in 12/75 1976

.482 386 114 62 33 10 20 2

0 1

1.112 630 1 34 0.21 Type - BWR; 786 MWe HUMBOLDT BAY DPR-7 1974 41 110 37 20 13 11 35 35 17 18 337 296 318 1.07 Commercial in 8/63 1975 3*

100 28 10 15 9

25 29 22 27 303 265 339 1.28 y Type - BWR; 65 Mde 1976 78 139 44 48 38 3G 66 89 32 37 601 523 683

1. 31 INDIAN POINT 1.*

1974 617 336 125 90 75 56 162 124 41 9

1 1.636 1.019 911 0.89

2. 3 DPR-5 26, 64 Commercial in 1975 744 330 141 Ba 57 53 110 49 29 27 7

1.635 8 91 705 0.79 10/62. 8/73. 8/76 Type - PWR; 265 1976 656 368 217 177 112 111 272 135 68 63 49 14 3

0 (10- 2.246 1.590 1.950 873. 965

11) 1 1.23 KEWAUNEE DPR-43 1974 181 95 44 31 15 11 6

383 202 52 0.26 Commercial in 6/74 1975 143 56 13 16 6

2 5

1 247 104 28 0.27 Type - PWR; 560 MWe 1976 84 87 56 57 49 30 79 21 2

465 381 270 0.71

• Indian Point I was defueled in 1975 9

APPEkOIX A LICENSED NUCLEAR POWER FACILITIES ANNUAL !.' HOLE BOCY EXPOSURES 1974,1975.1976 (Continued)

",d*

h Total In j Number of Individuals with Whole Body Enposures in the following Panges (Rems) y,g,y 1 1 PL AmT NAML AND Year No Ceas-Number Meas-Man ams Exposure-Rems LICENSE NUMBER Peasurable urable 0.10-0.25-0.50-0.75-1.0-

2. 0-

3. 0-4.0-

5. 0-

6. 0-

7. 0-8.0-9.0- Mont-urable Per Year (Measurable Exposure

<0.10 0.25 0.50 0.75 1.0 2.0 3.0 4.0 5.0 6.0 7.u 8.0 9.0 10.0 torea Exposure Per Site E s posures Only)

LACR055E DPR-45 1974 38 34 15 7

7 4

13 19 15 1

153 115 139 1.21 Conmercial in 6/74 1975 00 40 20 17 4

5 25 23 19 it 22b 165 234 1.42 Type - BWR; 50 MWe 1976 92 44 13

,2 7

4 30 14 4

210 118 110 0.93 MAINE YANKEE DPR-361974 4.374 362 32 35 28 22 63 44 17 10 3

2 1

4.993 619 420 0.68 Commercial in 12/72 1975 233 1 68 44 32 38 3'

84 39 5

613 440 319 0.73 Type - PWR; 790 MWe 1976 265 115 44 25 22 14 24 509 244 85 0.35

[j MILL 5 TONE POINT 1 1974 887 664 245 105 94 268 154 33

'8 6

1 3.477 2,477 1,430 0.55 DPR-65 Cnmmercial in 3/71 1975 906 686 629 354 212 99 317 130 70 48 24 10 7

3 3.495 2.5o7 2, 022 0.78 Type - 8WR; 690 MWe 1976 464 485 149 105 90 61 304 126 36 18 3

1,841 1,377 1,194 0.87 MILLSTONE POINT 2 1976 315 332 87 69 27 17 44 10 3

1 035 620 160 0.27 UPR-65 Lannercial in 12//5 T pe - PWR 828 MWe 3

MONTICEtt0 CPR-21 1974 467 362 130 137 78 51 55 22 6

1 1,309 842 349 0.41 Commercial in 6/71 1975 434 246 140 228 124 92 369 79

'7 25 7

e 2

1,787 1,353 1.353 1.00 Type - 8WR; 545 MWe 1976 407 97 47 E6 27 26 40 13 6

4 3

2 3

732 325 263 0.81

.m.

AFPE'iO!X A LICENSED NUCLEAR POWER FActtITIES ANNUAL WHOLE B00V EXP050RES 1974, 1975. 4976 (Continued)

A ber Number o' Individuals with Whole Body Esposures in the following Ranges (Rems)

Ajeage Total y,

PLANT NAME A40 Year No Meas.

Nunoer Meas-Man-rems Es posure-Rems LICENSE NUMBER Measurable urable 0.10-

0. 25-

0. 50' O.75-

1. 0-2.0-

3. 0-4.0-

5. 0-6.0-7.0-

8. 0-9.0- Moni.

urable Fer tear (Measurable Exposure

<0.10 0.25

0. 50 0 '5 1.0 2.0 3.0 4.0 5.0 6.0 1.0 8.0 9.0 10.0 tored Esposure Per Site Ex posures Onirl NINE MILL POINT 1974 463 224 95 83 39 24 111 93 24 26 17 4

1.203 740 824 1.1?

GPR-63 Commercial in 12/69 19/5 641 193 99 59 21 33 119 50 37 23 9

1.290 649 681 1.05 Tyre - BWR; 610 MWe 19/6 544 132 51 38 25 la 38 40 26 36 e

936 394 423 1.09 OCUNEL 1. 2, 3 1974 409 256 134 123 68 78 149 35 1

1.253 844 Sti 0.61 BJ DPR-38, 47. SS Commercial in 7/73. 1975 255 275 163-117 61 47 102 47 15 2

1.084 829 -

497 0.60 9/74. 13/74 Type - PWR; all 19/6 266 288 1d1 156 120 92 225 108 44 1

1.48 'r 1.215 1.026 0.84 886 FWe OYS7EK CREEK DPR-161974 109 207 140 110 33 41 203 77 30 27 14 1

1.104 935 984 1.05 Conmercial in 12/69 1975 264 439 157 119 69 59 202 56 43 26 24 10 1

1.474 1.210 1.140 0.94 Type - BWR; 650 MWe 1976 133 3 98 279 284 176 92 234 72 34 9

4 1.715 1.582 1.078 0.6P PALISADES OPR-20 1974 330 249 77 97 53 58 148 68 19 5

1.104 774 627 0.81 Commercial in 12/71 1975 149 204 70 51 36 29 57 38 9

1 644 495 306 0.62 Type - PWR; 821 MWe 19/6 144 227 67 94 40 47 138 99 18 12 B86 142 696 0.93

APPEN0!I A LICENSE 0 NUCLEAR PCWER FACILITIES ANNUAL WHOLE BODY EyPOSURES 1974. 1975. 1976 (Continued)

Ntaber of Individuals with Whole Body Exposures in the Following Ranges (Rems)

Total Total b

PLANT NAME AND '

Year No Meas-Number Meas-Man-rees E s pos ure-Rees LICENSE NUMBER Measurable urable 0.10- 0.25- 0.50- C.75-1.0-2.0-3.0-4.0-5.0-6.0-7.0-8.0-9.0- Moni-urable Per Year (Measurable Exposure

<0.10 0.25 0.50 0.75 1.0 2.0

3. 0 4.0 5.0

6. 0

7. 0 8.0 9.0 10.0 tored Exposure Per $tte Esposures Caly)

PEACH BOTTOM 2 & 3 1975 1.527 511 209 148 41 19 39 4

2.4 98 971 228 0.23 DPR-44, 56 Commercial in 7/74. 1976 1.349 855 356 341 215 173 173 19 4

3.485 2.136 840 0.39 12/74 Type - BWR; Both m 655 MWe Ln PILGR!M OPR-35 1974 363 105 70 65 46 28 83 31 12 6

3 5

817 454 415 0.90 Careercial in 12/72 1975 324 102 57 29 30 17 83 65 42 13 12 4

10 8 (10-797 473 798 1.69

11) 1 Type - BWRt 655 MWe 1976 56 105 104 90 60 140 281 200 149 105 40 29 12 2

1.373 1.317 2.643 2.01 POINT BEMH 1 & 2 1974 353 138 39 36 34 33 90 23 6

1 753 400 295 0.74 DPk-24, 27 Cornercial in 1975 274 65 32 32 27 17 79 46 19 16 5

1 613 339 459 1.35 12/70. 4/73 Type - PWR; Both 1976 T 28 55 38 28 34 20 70 44 15 6

3 as 31 3 370 1.18 497 MWe PRAIR!E ISLAND 1 & 1974 328 112 19 14 4

2 478 150 18 2.12 2 OPR-42.60 Cornercial in 1975 234 316 57 33 17 14 38 2

711 477 123 2.26 12/73. 4/74 Type -PWR; Both 1976 560 306 128 116 67 60 103 20 14 4

1.368 818 441 o.55

APPEND 11 A LifENSED NUCLEAR POWER FACILI7!ES ANN'JAL WHOLE BODY EXP050RES 1974,1975.1976 (Continued) kamber Average Number of Individuals with Whole Body Enposures 6n the Following Ranges (Rems)

Total with Total Individual PLANT NAME AND Veer No Meas.

~ ~ ~ ' - ~ ~ ~ ~ ~ ~ ~ ~ ~ N e<be r Meas. Man-rem < E s pe s ure-R ems LICENSE NUMBER Measurable urable 0.10-0.25-0.50-0.75-1.0-2.0-3.0-4.0-5.0-6.0-7.0-A.0-9.0- Mont-urable Per veer ( Measurable E s posure

• 0.10 0.25 0.5C 0.75 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 11.0 tored Is posure Per site E s posures Onh)

QUAD CITIES 1 & 2 1974 1,296 245 95 112 47 27 69 47 27 7

2 1,974 678 482 0.71 OPR-46, 60 Commercial in 2/73, 1975 1,225 113 64 1 08 74 92 337 18' 5(

33 23 2,308 1.083 1,618 1.49 3/73 Type - BWRt Both 1976 1,132 235 125 120 80 54 309 159 44 55 33 1

2,357

?,225 1,651 1.35 809 MWe tu RANCHO SECO DPR-54 1975 1,055 149 43 19 3

1 1

1,271 216 2f 0.12 Commercial in 4/75 1976 151 179 C2 26 15 6

9 443 297 58 0.19 Type - PWR; 913 MWe H. B. ROBINSON 2 1974 586 354 82 57 19 46 151 89 18 5

1 0

1 1,439 853 672 0.79 DPR-23 Commercial in 3/71 1975 599 230 50 55 52 67 138 172 33 30 21 1

1,448 849

',142 1.34 Type - PWR; 707 MWe 1976 60J 1 51 39 42 37 47 109 152 13 7

1,197 597 715 1.20 SAN ONOFRE DPR-13 1974 167 89 50 50 14 4

7 2

2 1

3R6 219 71 0.33 Commercial in 12/68 1975 393 124 63 72 43 27 51 34 9

1 817 424 292 0.69 Type - PWR; 450 MWe 1976 1,246 432 182 172 96 103 260 78 5

2 2,576 1,330 880 0.66

APPENDIX a LI.FNSED NuCLEAA P0mER r AcalltIE2 ANNUAc WHOLE BOOT EXPOSURES 1974. 1975. 1976 Number of Individuals with Whole Body Exposures in the Following Ranges (Rems)

Total w h Total In i idual PLANT NAME AND Year ho Meas-Number Meas-Man-rems Es posure-R ems LICENSE NUMBER Measurable urable 0.10-0.25-0.50- 0.75-1.0-2.0-3.0-4.0-5.0-6.0-7.0-8.D-9.0- Mont-urable Per Year (Measurable Esposure 0.10 0.25 0.50 0.75 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 tored Exposure Per Site Es posures

_Only)

SURRY 1 & 2 OPR-32. 1974 1.004 870 218 171 95 67 176 81 22 8

5 2

2.719 1.115 884 0.52 37 Commercial in 12/72 1975 58 0 813 145 158 108 98 314 247 33 18 7

6 1

528 1.948 1.649 0.85 Type - PWR; Both 1976 581 802 264 251 158 126 574 382 73 51 31 21 7

8 5 3.234 2.753 3.165 1.15 1/73 823 MWe na THREE MILE ISLAND 1974 541 123 87 37 5

4 1

798 257 43 0.17 OPR-50 2,ommercial in 9/74 1975 78 31 15 6

1 131' 131' 73' Type - PWR; R19 MWE 1976 901 290 221 107 55 107 33 6

1.720 819 286 0.35 TROJAN NPF-1 1976 514 473 62 27 11 5

1.092 578 56 0.10 Commercial in 5/76 Type - PWR; 1130 MWe TURKEY POINT 3 & 4 1974 876 225 182 138 62 46 85 44 11 1

1.670 194 454 0.57 OPR-31. 41 Commercial in 1975 849 361 173 117 130 71 211 82 22 8

1 2.025 1.176 876 0.74 12/72. 9/73 Type - PWR; Both 1976 1.013 457 317 232 156 92 230 96 48 17 2

2.660 1.647 1.184 0.72 745 MWe

'Did not report those not required to be monitored

s APPL 40!X A t!CENSIO huCLEAR POWER FACILI's!ES AN40AL WHOLE BODY EKPO5URES 1974. 1975, 1976 humber of Individuals with Whole Body Esposures in the Following Ranges (Rems)

Total m h Total Indi id al PLANT NAME AND Year ho Meas-Number Meas. Man-rems Exposure-Rems LICENSE hUMBER Measurable urable 0.10-0.25- 0.50-0.75-1.0-2.0 3.0-4.0 5.0 6.0-7.0-8.0-9.0- Ment-urable Per Vear (Measurable E x pc su-s

<0.10 0.25 0.50 0.75 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 tored Exposure Per Site Exposures Only)

VERMONT YANKEE 1974 576 137 60 lb 24 17 56 23 4

933 357 216 0.61 DPR-28 Commercial in 11/72 1975 773 60 87 42 24 27 27 13 2

1.055 282 153 0.54 Type - BWA. 514 MWe 1976 988 913 129 120 56 65 1 01 24 7

1,903 815 411 0.50 bc 00. Y ANFEE R0WE DPR-3 1974 3,060 137 60 36 19 23 56 23 7

3,333 243 205 0.84 Commercial in 1/61 1975 1.572 95 19 42 21 48 23 1

1,821 249 116 0.47 Type - PWR; 175 MWE 1976 986 50 23 41 16 9

13 1.138 152 59 0.39 ZION I & 2 OPR-29, 1974 1,657 168 80 34 15 6

2 0

1 1,963 306 56 0.18 48 Commercial in 1975 1,260 147 118 98 35 26 12 1.696 436 127 0.29 12/73. 9/74 Type - PWR; Both 1976 1,073 1 92 129 98 72 68 155 52 5

2 0

0 0

1 1,847 774 571 0.74 10?$ MWe 4

e

APPENDIX B OVEREXPOSURE SUMMARIES 1976 Industrial Radiography - License Number 35-16191-01 On February 7,1976, a radiographer and his assistant were conducting radiography operations in a vault at a field location using a 97 curie iridium-192 source. After the last exposure of the day, the source was retracted and the assistant radiographer entered the vault, surveyed the back side of the exposure device and retrieved the equipment.

The fact that the source was not fully retracted was not discovered until shortly thereaf ter when it was noted that the assistant's dosimeter was discharged.

This was reported and the assistant's film badge was sent for immediate processing.

The results indicated a whole body dose of 5 rems.

He was not allowed to work in radiation areas for the remainder of the quarter and he was reprimanded and retrained.

On April 27, 1976, the same radiograoher and another assistant were conducting similar radiography operations at the same location.

The assistant entered the vault to retrieve the exposed film cassettes without knowing that the source was not fully retracted.

The results of his film badge processing indicate a whole body dose of 5.5 rems.

The corrective actions were the same as those given far the firs' incident.

See also NUREG-0090-4, " Report to Congress on Abnormal Oc'.urrences."

29 a

4

.i Appendix B (Cont'd)

Industrial Radiography - License Number 35-15194-01 J

During routine processing of the film badges for August 1976, it was discovered that the badge of one of the radiographers indicated that he l

may have received 22.8 rems to the whole body.

Investigation of the

{

indicated overexposure revealed no specific event that could be definitely identified as the cause of the high reading.

However, the radiographer did state that his pocket dosimeter was off-scale at the end of the work shift on August 4,1976, anf he did not record this on his dosimeter records nor notify his supervisor.

He worked from August 2 through August 10, 1976, at which time he was terminated.

The radiographer was i

medically examined and no adverse clinical findings were evident.

Corrective actions included an increased audit program by management and i

the establishment of disciplinary action for failure to follow company i

procedures. See also NUREG-0090-6, " Report to Congress on Abnormal Occurrences."

Industrial Radiography - License Number 37-02607-02 On November 12, 1976, a radiographer was conducting in-plant radiography operations using a 94 curie iridium-192 source.

After completing a radiograph, he approached the projector to disconnect the source tube.

After he had unscrewed the source tube and pulled it away, he saw that 4

the source was still approximately one foot outside the projector. The radiographer then returned and cranked the control cable to fully retract

.the source.

The.results of the radiographer's film badge analysis and

' subsequent time and motion studies indicated that he may have received 30

Appendix B (Cont'd) 5.38 rems to the whole body and from 450 to 3700 rems to the hands.

The employee was reprimanded and reinstructed in the use of radioactive sources.

See also NUREG-0090-6, " Report to Congress on Abnormal Occurrences."

Industrial Radiography - License Number 37-00453-03

' On July 13, 1976, while conducting in-plant radiography operations using a 71 curie cobalt-60 source, the radiographer found that his survey

)

. meter and his pocket dosimeter had gone off-scale.

He quickly walked out of the room, cranked the source into its shielded position and called his supervisor.

Investigations revealed that he had failed to retract the source or perform a survey when he first entere ' the are6.

Time and motion studies indicated that the radiographer could have received 11 rems to the lens of the eyes and 5.5 rems to the abdomen.

Medical studies failed to reveal any evidence of radiation injury.

HowcVer, the radiographer was restricted from radiation areas for the remainder of the quarter.

Corrective actions included the improvement of the company's internal audit program and the installation of gamma activated alarms in each exposure cell.

See also NUREG-0090-5, " Report to Congress on Abnormal Occurrences."

i Industrial Radiography - License Number 42-02808-04 On December 12, 1976, while conducting radiography operations at an in-plant shielded radiography cell, the radiographer realized that he may have been overexposed when he found that the 166 curie cobalt-60 source was already in the " exposed" position.

He completed the radiograph in progress, cranked the source into its shield and initiated emergency 31 i

I

.~..

Appendix B (Coat'd) procedures.

Subsequent investigations revealed that film badges and pocket dosimeters, although available, had not been worn by either the radiographer nor his project technician; the radiographer could not remember reading his survey meter as he entered the cell for his last set-up; the door interlocks, warning horn and area monitor had been manually deactivated.

Therefore, it could not be definitely concluded that an overexposure had or had not occurred and possible dose deter-minations had to be based on time and motion studies.

The results indicated that the radiographer may have received 9 rems to t'.e lens of the eye and 1500 rems to his hand.

His project technici = " lay have received 4 rems to the lens of the eye.

The Commission halted all radiography operations at the facility until appropriate corrective actions were initiated and inspected.

See also NUREG-0090-6, " Report to Congress on Abnormal Occurrences."

Industrial Radiography - License Number 20-01074-02 On November 3,1976, a radiographer conducting radiography operations with a 30 curie iridium-192 source at an airport jobsite terminated work early because he had begun to feel ill.

In his haste, he failed to completely retract the source to its shielded position in the exposure device betore he placed it in his mobile van.

The radiographer drove the van to several locations in the Boston area and parked the van at his residence overnight.

The next morning he picked up his assistant radiographer who shortly thereafter turned on a survey meter which was in the driver's compartment.

He found the readings of the survey meter 32

Appendix B (Cont'd) to be off-scale on all ranges.

They stopped the van and retracted the source to its safe position.

Subsequent investigations and evaluations indicated that the radiographer received 10.3 rems to the whole body.

His assistant was not overexposed and no member of the general public received a significant exposure.

The radiographer was restricted from radiation areas for the remainder of the quarter and all radiography personnel completed a radiation safety refresher course.

See also NUREG-0090-6, " Report to Congress on Abnormal Occurrences."

Industrial Radiography - License Number 04-00616-04 On January 8,1976, after completing radiography operations at a job site in Utah, a radiographer reported that his pocket dosimeter reading was off-scale.

The radiation safety officer concluded that the dosimeter was defective and he issued the radiographer another onc.

On January 14, 1976 the radiographer again reported an off-scale reading and his film badge was sent for processing.

Although the radiographer reported that on neither occasion did anything unusual occur, the film badge was found to indicate a whole body dose of 6.9 rems for the period of January 1 through January 14.

All personnel assigned to the Utah jobsite were required to complete a radiation safety refresher course.

Nuclear Power Facility - License Number DPR-39 On March 17, 1976, after three attempts had failed to locate the pathway of the water leaking from the refueling cavity into the reactor cavity, a management person made arrangements to enter the cavity area.

He had 33

Appendix B (Cont'd) to carry an integrating type survey meter and was to leave the area before it read 0.500 rems.

He proceeded to enter the cavity and began inspecting, noting the reading on the meter every few minutes.

He did not find the leak in the first area and began an inspection of the annulus between the reactor vessel and the concrete shield wall.

During this inspection he noticed that his survey meter was off-scale and he imediately left the area.

Evidently, the withdrawal of the in-core detector thimbles from the reactor vessel had increased the radiation levels considerably.

Subsequent processing of the individual's film badge indicated a whole body dose of 8.05 rems.

Corrective actions included the establishment of stronger administrative controls on the access to the cavity area during shutdown and the participation of all station personnel in a radiation protection retraining program.

See also NUREG-0090-3, " Report to Congress on Abnormal Occurrences."

Nuclear Power Facility - License Number DPR-26 On April 5,1976, during a refueling outage, a nuclear plant operator (NP0) entered the Unit 2 reactor vessel sump room to replace light bulbs to illuminate the area for maintenance activities.

The last field survey had indicated that the radiation levels were low enodgh for an individual to enter and complete the job.

However, between the time of the last survey and the time that the individual entered the sump, radioactive in-core detector thimbles had been withdrawn from the reactor vessel.into the sump area.

Unaware that the radiation level had increased considerably, the NP0 proceeded into the sump level.

After a 34

Appendix B (Cont'd) short time he checked his pocket dosimeters and found them to be off-scale. He immediately left the area and reported the incident.

Subse-quent processing of the NP0's film badge indicated a whole body dose of 10.06 rems.

Corrective actions included the partial reinsertion of the detectors into the reactor vessel, thereby lowering the radiation level, and installation of a radiation monitor in the area to alert personnel to increases in radiation fields.

See also NUREG-0090-4, " Report to Congress on Abnormal Occurrences."

Industrial Radiography - License Number 42-16559-01 On November 4,1976. two radiographers were radiographing the vertical seam of a large steel cylinder section of an oxygen furnace using a 47 curie cobalt-60 source at a customer's location.

During the ninth of a series of exposures both radiographers noticed that their pocket dosimeters were off-scale.

Evidently the radiographers had failed to make the proper surveys and they had entered the cylinder and been in close proximity of the source while setting up for the next radiograph.

l Attempts to retract the source to its shielded position were unsuccessful and the radiation safety officer was called. to the site.

He subsequently I

retracted the source without difficulty.

Re-enactment of the radiographic operations indicated that one radiographer may have received 15.7 rems to the whole body and a maximum of 1700 rems to the hands.

The other radiographer may-have received 1.7 rems to the whole body and a maximum of 840 rems to the hands.

35

Appendix B (Cont'd)

The Commission halted all radiography operations by the licensee until appropriate corrective cctions were determined and field site inspections were completed.

See also NUREG-0090-6, " Report to Congress on Abnormal Occurrences."

Radiography Operations - License Number 35-13735-01 I

On October 9,1976, after completing several radiographs, an assistant radiographer discovered that his pocket dosimeter was off-scale.

Upon reporting this, the assistant radiographer's film badge was sent for

{

processing.

The results indicated that he may have received 5.62 rems to the whole body.

Evidently the overexposure had occurred when, after making a proper survey, the assistant moved the control cranks a little as he carried the projector to a new position. All radiography personnel have been instructed to carry a survey meter with them and re-survey any time a projector is moved to another set up.

Industrial Radiography - License Number 42-16559-01 On July 8,1976, five individuals were overexposed while conducting in-plant radiography operations.

On the day of the incident there were two 3

shi,fts of two men which overlapped. At the termination of the shift, the first two radiographers left without retracting the 44 curie cobalt-60 source that they had been using into its shield; the second shift continued using their 92 curie iridium-192 source.

Subsequently, when one of the radiographers wanted to use the cobalt-60 source, he found that it was unshielded.

He ininediately left the exposure vault and in 36 l

Appendix B (Cont'd) his haste, he cranked out the iridium source, thinking that he was retracting the cobalt source.

Since both sources were now exposed, attempts to reduce the radiation to a safe level by working with the cobalt exposure device failed.

The first shift was called back and two other individuals also attempted to rectify the situation before it became apparent that the iridium was the source of the high radiation levels and was retracted into its shield.

The failure of the men to adhere tu approved operating and emergency procedures resulted in Individual "A" receiving 24 rems to the v: hole body and 43 rems to the hands; Individual "B" received 6.7 rems, whole body; Individual "C"

received 3.8 rems, whole body; Individual "D" received 6.7 rems, whole body; Individual "E" received 1.45 rems to the whole body and 20 rems to the hands.

Corrective actions included the retraining and testing of the involved individuals and the installation of an automatic detection device for the exposure vault.

37

UNITED STATES 1

{

]

j NUCLE AR REGULATORY COfAMISSION W ASHINGTON, D. C.

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