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Idaho National

Engineering Laboratory

1 1

INEEL/EXT-98-00148 (1st QTR)

May 1998

Idaho National Engineering and Environmental Laboratory Radiological Control Performance Indicator Report

First Quarter - Calendar Year 1998

Date Published May 1998 3

L O C K H E E D

F..

DISCLAIMER

This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof. nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or use- fulntss of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, proctss, or service by trade name, trademark, manufac- turer, or otherwise does not necessarily constitute or imply its endorsement, recorn- mendation. or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

DISC LA1 M ER

Portions of this document may be illegible in electronic image products. Images are produced from the best available original document.

INEEL/EXT-98-00148 (1st QTR)

Idaho National Engineering and Environmental Laboratory

Radiological Control Performance Indicator Report

First Quarter Calendar Year 1998

Published May 1998

Idaho National Engineering and Environmental Laboratory Radiological Control

Lockheed Martin Idaho Technologies Company Idaho Falls, Idaho 83415

Prepared for the U.S. Department of Energy

Assistant Secretary for Environment, Safety, and Health Under DOE Idaho Operations Office

Contract DE-AC07-94ID13223

Document Title:

Prepared By:

Approved By:

Idaho National Engineering Laboratory Radiological Control Performance Indicator Report

F. L. Hinckley

Manager, Radiological Control

05-21 -98 Date

05 -2 1 -98 Date

TABLE OF CONTENTS

Charter ............................................................................................................................... 2

Executive Summary ............................................................................................................ 3

INEEL Overview ................................................................................................................ 6

.. Facility Overview ................................................................................................................ 8

Criteria ............................................................................................................................. 10

INEEL Report ........................................................................................................... 12-18

Facility Reports

Central Facilities Area (CFA) ....................................................................................... 19-24

Idaho Nuclear Technology and Engineering Center (INTEC) ....................................... 25-30

.. Power Burst Facility (PBF) .......................................................................................... 3 1-36

Radioactive Waste Management Complex (RWMC) .................................................... 37-42

Test Reactor Area (TRA) ........................................................................................... .4 3-48

TRA Hot Cell (MAC-I) ............................................................................................... 49-54

Test Area NortWSpecific Manufacturing Capability (TANISMC) ................................. 55-60

1

Radiological Control Performance Indicator Charter

The INEEL Radiological Control Performance Indicator Report is provided quarterly, in accordance with Article 133 of the INEEL Radiological Control Manual. Indicators are used to measure performance of the Radiological Control Program and as a motivation for improvement, not as goals in themselves. These indicators should be used by management as tools to focus priorities, attention, ahd adherence to As-Low-As-Reasonably-Achievable (ALARA) practices.

The ALARA Committees establish ALAM goals for the INEEL based on forecasts and goals provided by each facility organizational manager or supervisor.

Performance goals are realistic and measurable. Stringent goals are set at least annually to reflect expected workloads and improvement of radiological performance. Goals higher than previous goals may occasionally be set due to changes in work scope or mission.

The INEEL Radiological Control Performance Indicators consist of

0 Collective dose in person-rem.

0 Average worker dose, maximum dose to a worker, and maximum neutron dose equivalent to a worker.

Number of skin and clothing contaminations, including the number of contaminated wounds and facial contaminations.

0

0

0

These indicators also provide tracking and trending for the previous three years.

Other Radiological Control indicators suggested in the Radiological Control Manual are tracked and trended in other reports.

Number of radioactive material intakes resulting in a dose assessment of 10 mrem or more.

Area of Contamination, High Contamination, and Airborne Radioactivity Areas, in square feet.

Airborne radioactivity events and spills.

The Environmental Management Operations Support Department reports the volume and radioactivity content of radioactive waste in the INEEL Radioactive Waste Management Annual Report and on the Radioactive Waste Management Information System (RWMIS).

Releases of liquid and airborne radioactivity discharges are reported by the Environmental Affairs Branch in the INEEL Environmental Monitoring Report and the INEEL National Emission Standard for Hazardous Pollutants ( NESHAPs) - Radionuclide Annual Report.

/

2

Executive Summary Radiological Control Performance Indicator Report

First Quarter 1998

This document provides a report and an analysis of the Radiological Control Performance Indicators through the first Quarter of Calendar Year 1998 (CY-98) for Lockheed Martin Idaho Technologies Company (L,MITCO). LMITCO is the prime contractor at the Idaho National Engineering and Environmental Laboratory (INEEL). This Performance Indicator Report is provided in accordance with Article 133 of the INEEL Radiological Control Manual.

The INEEL collective occupational radiation deep dose is 12.426 person-rem year to date, compared to a quarterly goal of 16.2 person-rem. In comparison to last year, the site dose goal has been reduced mainly due to work scope reductions at the Idaho Nuclear Technologies and Engineering Center (INTEC), formerly the Idaho Chemical Processing Plant. Due to unforeseen increases in shipments to the Radioactive Waste Management Complex, we anticipate additional dose increases and will reflect these changes in the next quarter report. The chart below shows the facility comparison.

40.0

30.0

E e 6 20.0

t P

10.0

0.0

Jan-March

1 6 2

6.3 5.9 6.4 - 2.5 2.6

0.1 0.45 0.1 0.3 n . - .

CFA lmc PBF RWMC m TANlSMC LMrrco BVD UMDGoal

3

Beginning CY-98, a numeric Radiological Performance Index (RPI) will be used to compare radiological performance. The RPI takes into consideration frequency and severity of undesirable events such as skin contaminations, clothing contaminations, spills, exposures to radiation exceeding limits, and positive internal dose. The RPI uses cost coefficients which approximates the total cost (e.g., investigations, sampling, down-time) per the event.

Variable Description D

ROE

AOE

SCE

UR

AEE

CCE

Number of deaths due to acute radiation exposure

Number of administrative over exposures (>2 rem TEDE)

Number of regulatory unplanned over exposures (>5 rem TEDE)

Number of skin contamination events Number of uncontrolled releases of radioactive material or radioactive con&ination outside of radiologically controlled areas

Number of clothing contamination events

Radiological Work Permit (RWP) hours = Total hours worked on RWPs

Number of exposures above expected exposures by >lo0 mrem (TEDE)

PB Number of positive bioassays

F

The RPI is calculated as follows:

Cost Coefficient 1,000,000

500,000

200,000

25,000

25,000

10,000 5,000

2,000 RWP hours

RPI = 1OO[(1,OOO,OOO*D)+(5OO,OOO*ROE)+(2OO,OOO*AOE)+(25,OOO*SCE)+(2S,OOO*~)+(lO,OOO*~E)+(5,OOO*CCE)+(2OOO*PB)] F

In the “F” section of the calculation, Radiological Work Permit (RW) hours have not been available until CY-98, and are one of the products of the Radiological Control Information Management System (RCIMS) implemented this year. During the first quarter there were 73,419 RWP hours.

To make the RPI meaningful, tables have been prepared to show the facility that contributes to the values used in the formula above. The data is compared on a quarterly basis to the prior year’ to show measurable performance.

The values for CY-98 and CY-97 are shown in the tables on the next page, as well as a chart to be used to establish a baseline from the performance indicators and RWP hours.

4

.-

The following table provides the values used in the RPI calculation and the facility contributing to those values. CY-97 values are provided as a comparison.

CY-97 First Quarter Contributors

The following chart will be used to compare quarterly data during this year as a baseline is established.

Radiological Performance Index 140 1 11 5.8 CY-98

120

Istqtr. 2nd qtr. 3rd qtr. 4th qtr.

CY-95 was LMITCO’s first full year at the INEEL. By using the CY-95 first quarter performance values, and estimating what the RWP hours may have been, we have postulated a RPI number of 621.1 for CY-95.

5

INEEL Radiological Control Performance Indicator Overview first Quarter 1998

Collective Year-to-Date Penetrating Radiation Dose

Year-to-Date Average Worker Dose

Maximum Year-to-Date Penetrating Dose to a Worker

Maximum Year-to-Date Neutron Dose to a Worker

Year-to-Date Skin Contaminations

,... . . N @ .::, .: .

Legend

Actual Goal or Average

person-rem person-rem 12.426 95.63

(Goal)

0.028 0.1 16 rem rem

(3 Year Average)

.218 rem

0.030 rem

2

1.500 rem (Goal)

0.1 10 rem (3 Year Average)

23 (3 Year Average)

Needs Attention Compared to three yr. Avg/goal.

Good

6

Actual Goal or Average

- Year-to-Date

Clothing Contaminations

Year-to-Date

Airborne Events

Year-to-Date

Radioactive Material

Intakes

i.. . ...... p &1 y f

p &,

p &t

_. ....

Contamination Area

High Contamination

Area

Airborne Radioactivity Area

Year-To-Date

Spills

2 41 (3 Year Average)



199,450 I 93,21 a ft2 ft2

(3 Year Average)

297,901 297,767 ft2 ft2

(3 Year Average)

84,442 84,837 ft2 ft 2.

(3 Year Average)

I a ......... @ /

16 (3 Year Average)

7

INEEL Facility Radiological Control Performance Indicator Overview first Quarter 1998

Needs Attention OK

PBF RWMC TRA TAN/SMC

Collective Year-to-Date 0 0 0 0 0 0 Penetrating Radiation Dose (person-rem).

0.085 5.919 0.115 2.540 2.954 1.244

@ %*

@ goal Compared to three yr. Avg. or

Year-to-Date Average rl rl ri ri 3 Worker Dose (rem) 0 0 0 8 0 0 @ @ B O

0.005 0.029 0.009 0.046 0.027 0.028

Maximum Year-to-Date penetrating dose to workers is redundant to facility reports and is

not repeated in this report. I

Maximum Year-to-Date neutron dose is no longer reported for facilities in this report. ' . Year-to-Date

Skin Contaminations

0 1 1 0 0 0

Legend

\- I

8 I

RWMC TRA

0 &t 0 .........

PBF

0 0 &, ...... - 0

INTEC

2

Year-to-Date

Clothing Contaminations

0 0

@ 0

0

. 2.. @ .:., ....

0

..... &, ::., ..<

0

10,240

@

29,525

0

@

0

...... :I* @

Year-to-Date Airborne Events

0

@ 0

0

q @ ., .... .:..

Year-to-Date

Radioactive Material

Intakes 0

El Kl 53,226

11,526

0 0

7,378

2,288

(8 ..... E Contamination Area

- ft2

49,682 64,819

Io High Contamination

...... i o &t 2 Area - f %

2,601

0

1

251,961 ~

0

......... ! @ 0

Airborne Radioactivity Area -ft

2

0 2,000

p 6?, 0

82,442

0

..... p; @ .:., i.

0

Year-to-Date

Spills I

1 0

9

Radiological Control Performance Indicator Report Criteria

The INEEL Radiological Control Performance Indicator Report is comprised of a description of the indicator and the criteria used for measurement.

Collective Radiation Dose - The INEEL collective total penetrating radiation exposure received and the associated quarterly and annual ALARA goals.

Average Worker Radiation Dose - The average penetrating radiation dose based on collective dose and the total number of personnel receiving measured radiation exposure.

Maximum Radiation Dose to a Worker - The highest penetrating radiation dose received by a worker at the INEEL.

Maximum Neutron Dose to a Worker - This indicator reports the highest neutron radiation dose equivalent received by a worker.

Number of Skin Contaminations - The total number of radioactive skin contaminations and the number of those contaminations resulting in an Occurrence Report, the number of facial contaminations, and the number of contaminated wounds.

Number of Clothing Contaminations - The total number of radioactive clothing contaminations and the number of those contaminations resulting in an Occurrence Report.

Airborne Events - The number of occupied facility areas not posted as Airborne Radioactivity Areas that exceed 10% Derived Air Concentrations (DAC).

Total Year-to-Date Intakes - The number of positive bioassays that indicate an intake of radioactive material resulting in a dose assessment of 10 mrem or more fiom an INEEL occupational exposure. The total number of positive bioassays that resulted in an Occurrence Report are also tracked and trended.

_-

lo

Contamination Area - The total area in square feet that falls within the description of a Contamination Area as defined in Table 2-3 of the INEEL Radiological Control Manual.

High Contamination Area - The total area in square feet that falls within the description of a High Contamination Area as defined in Table 2-3 of the INEEL Radiological Control Manual.

Airborne Radioactivity Area - The total area in square feet that falls within the description of an Airborne Radioactivity Area as defined in Table 2-3 of the INEEL Radiological Control Manual.

Radioactive Spills - The total number of radioactive spills at the INEEL. A spill is considered an inadvertent loss or release of radioactive contamination outside a Radiologically Controlled Area.

11

200

0 0

IN EEL CY-98 Year to Date Collective Penetrating Radiation Dose -

~ v a a n e = ~ ~ . ~ D a s m r e m I 350,

95 96 97

95.6

.- -_._.*--- -2.4

.-- 1st Qtr 2nd Qtr 3rd Qtr

-Actual Dose - - - - - - - Atara Goal

4th Qtr

DOE and LMITCO policy is to maintain occupational radiation exposure as low as reasonably achievable (ALARA). The above chart provides a comparison of the INEEL goal and the total year to date collective penetrating radiation dose.

The CY-97 ALARA goal is 95.63 person-rem. The year to date total is 12.426 person-rem. The step increase in the goal is based on projected work scope at the INTEC.

The collective exposure is well below the goal primarily due to limited work during this quarter. Work scope is planned to increase during the next three quarters.

The INEEL Performance Indicators are designed to reflect a challenging, yet positive control of occupational radiological work.

This chart and the charts on the following pages provide an indication of how well LMITCO is performing as a company. Following the company charts are charts showing the six specific facility areas and their performance in selected indicators.

12

0.5

0.4

INEEL CY-98 Year to Date Average Worker Dose

0.1

0.3

E g!

0.2

- - 0.028

0 -

95 97 1

1 ..

0.21 8 0

0 1st Qtr 2nd Qtr

3rd Qtr 4th Qtr

The Average Occupational radiation dose for INEEL workers through the end of the first quarter was 0.028 rem based on 443 workers who received dose greater than 10 mrem.

INEEL CY-98 Maximum Year to Date Penetrating Dose to a Worker

5

0 1 st Qtr 2nd Qtr 3rd Qtr

-. .--. . Admen. - Actual

4th Qtr

The Maximum penetrating radiation dose to a worker through the end of the first quarter was .218 rem. The dose resulted from activities associated with ATR outage activities.

13

INEEL CY-98 Maximum Year to Date Neutron Dose to a Worker

0.4

2 5 -

0

E 5 15 L

0 E 0 L 0 10

n

z 5 5 - -

O *

Avorap= O.1 l ra

ORAvasgc=23

10

10

- - 10 20-;L s5 s¶ 9I

2

0.030

0 0 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr

-Total Number - - - - - - - Occurrence Report

There were two skin contaminations at the INEEL during the first quarter. Both were ORs. One at the PBF, and one at the INTEC. There were no facial contaminations or contaminated wounds.

14

60 u) C 0

m C

- U

140 U

I=

8 c,

L 0 u

20 3 z

0

INEEL CY-98 Year to Date Clothing Contaminations

0

ORAvaags=41

MI

95 96 97

6

1 st Qtr 2nd Qtr 3rd Qtr Total - - - - - - - Occurrence Report

4th Qtr

There were six clothing contaminatioris at the INEEL during the first quarter. Two were ORs. Details are contained in the facility report sections.

0

INEEL CY-98 Year to Date Airborne Radioactivity Events

Avua pa = 0

0 0 I ---.

95 96 97

1 0

0 1st Qtr 2nd Qtr 3rd Qtr

Total . - - . . - - Occurrence Report

4th Qtr

There have been no airborne radioactivity events during the first quarter.

15

L.

6--

4

2

0 1

E z

0

- -

- - 0 0

1st Qtr 2nd Qtr 3rd Qtr

htakes > IO wem - - - - - - - Occurrence Report

4th Qtr

Radioactive material intakes depict the number of positive bioassays that result in a dose assessment of 10 mrem or greater. So far year to date there have been no internal doses.

L

199.5 a 189.2 u 200.0 0

0.0 1 0 1st Qtr 2nd 3rd Qtr

Qtr -Total Cont. Area - - - - - - - Permanent in use

4th QlR

The total area designated as Contamination Area at the end of the first quarter was 199,450 square feet. The increase is from containers at the RWMC. These are being decontaminated. 150,800 square feet is designated as permanent and in use.

16

1Ooo.o *

8oo.o

8 0 ;; 600.0

f 400.0 c i a U rn

200.0

0.0 I

::mi 200

-. *o

0 €5 96 97 - -

297.9 297.9 - 296.6 296.6

.-

0

bi al L

5 '00.0 a U rn

50.0

0.0 '1

1st Qtr

95 96 97

"84.7 84.4

83.7 83.7 .i

- -

4

2nd Qtr

3rd Qtr 4th Qtr

-Total Hgh - - - - - - - Wrmanent in use

Total High Contamination Area at the end of the first quarter was 297,901 square feet. 296,641 square feet is designated as permanent or in use, such as the sizing facility at WERF.

The total Airborne Radioactivity Area at the MEEL at the end of the first quarter was 84,442 square feet. 83,662 square feet is designated as permanent and in use. The reduction is fiom work clean-up at the INTEC (formerly the ICPP).

17

INEEL CY-98 Ye 30,

ti E 15-- Q

S z

10

5

- -

- -

21

OR Avsiape 4 6

22

95 €3 97

2

0 0 1st Qtr 2nd Qtr 3rd Qtr

Total Wmber - - - - - - - Occurrence Report /

4th Qtr

There were two spills considered to be loss of control of radioactive material during the first quarter. One from TAN was an OR.

The three-year average noted on this chart represents only those spills that were reportable as ORs in prior report years.

18

Central Facilities Area

The CFA Facility report also includes other outlying area infomation

1. The major activity contributing to radiological exposure so far this year has been Decontamination and Decommissioning, Environmental Restoration, sampling, and facility maintenance.

2. Work scope at the CFA is basically similar to that of last year. Radiological work is expected to increase as the weather allows for more outside work.

19

6

5

4

k 3

E e!

0

0. f

2

1

0

CFA CY-98 Year to Date Penetrating Radiation Dose

Avaraps = 3.7 r a n 4 1 4.4

95 96 97

1.71 I .34 __._.*.--- ---. - - - - -

0.89 ___.___.- - - - - - __-__-. - - - - _- .- - - - - 0.45

0 I st Qtr 2nd Qtr 3rd Qtr Actual - - - - - - - Goal

4th Qtr

The collective penetrating occupational radiation exposure at CFA through the end of the first quarter is 0.085 person-rem. The major contributor has been Decontamination and Decommissioning @&D) at ARA

0.14

0.1 2

0.1

0.08

0.06

0.04

0.02

0

E 2!

CFA CY-98 Year to Date Average Worker Dose

45 96 97

0.005 I -

0 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr

The CFA average worker dose through the end of the first quarter was 0.005 rem evaluating dose from 16 workers with dose greater than 10 mrem.

20

CFA CY-98 Year to Date Skin Contaminations

5,

ORAverage=O :rl 0 1

05 96 97

0 0


Total Number - - - - - - - Occurrence Report

4th Qtr

There were no skin contaminations at CFA areas through the end of the first quarter

5

CFA CY-98 Year To Date Clothing Contaminations

4 OR Avacaoe =O

I L I 0 1

94 85 96


-Total - - - - - - - Occurrence Report

4th Qtr

There were no clothing contaminations at CFA areas through the end of the first quarter.

21

CFA CY-98 Year to Date Airborne Radioactivity Events

10

8

I x s 6 - c

b 0

$ 4 E a z

2

0

- v) c z 3

: E

W c

a8 Q 2

2

1

0 1

0

5~

5 ORAvataw 4

4 : : : r l 2

0 95 98 97

- -

- -

0 0

CFA CY-98 Year to Date Radioactive Material Intakes

ORAvorsga =O ;rl 95 96 97

0 0

1st Qtr 2nd 3rd Qtr 4th Qtr

Qtr

htakes >10 mrem - - - - - - - Occurrence Report

There were no positive bioassays indicating a radioactive material intake that resulted in a dose assessment of 10 mrem or greater at CFA through the end of the first quarter.

22

24 25 Avaipe=i5,103q.fl.

0 0.0 I

a

m--

200

0

0

95 96 97

- -

0 0


Total Cont. Area - - - - - - - Rrmanent in use

4th QTR

The total Contamination Area at CFA at the end of the first quarter was 14,105 square feet. None of this area was designated as permanent and in use.

0 1st Qtr 2nd 3rd Qtr Qtr

Total Hgh - - - - Permanent in use

4th Qtr

There are no High Contamination Areas in the area controlled by CFA personnel through the end of the first quarter.

23

CFA CY-98 Airborne Radioactivity Area

94 95 97


Total Airborne - - - - . Permnent in use

Currently, there are no Airborne Radioactivity Areas in CFA facility areas.

5

4

3 tj

“ 2

P

5

1

0

I CFA CY-98 Year to Date Spills I

4th Qtr

95 96 97

0 0

0 1st Qtr 2nd Qtr 3rd Qtr Total Number - - - - - - - Occurrence Report

4th Qtr

CFA had no radioactive spills or loss of control of radioactive material during the first quarter.

24

Idaho Nuclear Technology And

. Engineering Center

Formerly

Idaho Chemical Processing Plant

INTECSUMMARY

1. Major contributors to first quarter occupational radiation exposure were activities related to the CPP-640 ROVER completion, ROVER fuel movement and storage at CPP 603, NWCF operations, and WCF RCRA closure.

2. Details of two clothing contaminations that occurred during the first quarter are contained in OR ID-LITC-WASTEMNGT-1997-0027 and ID-LITC-WASTEMNGT-1997-0030.

3. There was one reportable skin contamination during the first quarter. OR ID-LITC- PHASEOUT-1998-0001 contains the detail.

4. There were no reportable spills during the first quarter.

25

100

E e! $ 5 0

E U

0

0

INTEC CY-98 Year to Date Collective Penetrating Radiation Dose

333

250

95 97

-- .* .- .- a - .- .-

6.4 .--e .- -*

) C ' -9

1st Qtr 2nd Qtr Goal - Actual _ _ _ _ _ _ _ 3rd Qtr 4th Qtr

The INTEC collective penetrating occupational radiation exposure through the end of the first quarter was 5.919 person-rem. Work scope change at the INTEC is much less this year than in years past. It is expected to increase for the next two quarters Application of ALARA protective measures in planning helps account for the lower goal.

INTEC CY-98 Year to Date Average Worker Dose

0.8 - - OAO

0.6 om I E e! 0.4

O** t

0.x)

om

I Aveiags 9.l8Oiem

0.25

95 96 97

0.029 0


The average worker dose for the INTEC through the end of the first quarter was 0.0.029 rem resulting from 207 workers receiving dose greater than 10 mrem. Work scope will increase during the second and third quarters.

26

15

v) e: 0 - c 2 10

z m S 0 0 0

c

.-

P s 5

5 z

0

0

INTEC CY-98 Year To Date Skin Contaminations

Average 40 ORs 25

2 0 % 1

5 lhhd 0

m 96 97 l T d i l OQZ

I

1st Qtr 2nd Qtr 3rd Qtr 4th Qtr -Total wmber _ _ _ _ _ _ _ _ _ _ _ Occurrence Report

The INTEC had one-reportable skin contaminations during the first quarter. There were no facial contaminations or contaminated wounds. Details are on OR# ID-LITC-PHASEOUT-1998-0001.

31

v) S 0

m - L

E 20 E s m S c

c 0

aJ n

3 z

L. 10

E

0

INTEC CY-98 Year to Date Clothing Contaminations

=J7-y-- I 20.0

10.0 w.olLLl 0.0

95 96 97

3


Total bhrnber - - - - - - - Occurrence Reports

Three clothing contaminations occurred during the first quarter at the INTEC. Two were reportable. Details are contained on OR ID-LITC-WASTEMNGT- 1998-000 1 and ID-LITC- PHASEOUT-1998-0002

27

5

L : 4 . -

E z 2

0 7

INTEC CY-98 Year to Date Airborne Events

1

95 96 97

- -

0 0

4

L

L 0

0) P

z E 2

1

95 96 97 I .

lo 0 0


No airborne activity greater than 10 % DAC in unposted areas was detected in INTEC areas during the first quarter.

INTEC CY-98 Year to Date Radioactive Material Intakes

10


htakes> 10mrern - - - - - - - Occurrence Report

There have been no dose assessments greater than 10 mrem CEDE for the first quarter.

28

200.0 *

150.0 8

t 100.0

0 .- x CI

U

fi

50.0 E

Avsraps=65.17jq.ft. ::: I-z-z-7

800.0 -

~ . o 0 0 0 .- x +.)

$ 400.0

f U

a

v, 200.0 U

0.0

95 96 97 t

2;I:lma AVMap~=251,961Sl.fl.

f 2

100.0

0.0 95 96 97

- _

2520 252.0

246.1 ._ 251.3

1

0.0 4 0 1st Qtr 2nd Qtr 3rd Qtr

Total Contaminated -----------Permanent

The total High Contamination Area at the rN"TEC was reduced by 270 square feet to 251,961 because of grouting activities at the WCF. 246,071 square feet are designated as permanent and in-use.

29

250.0

10

5

200.0

- -

- -

0

8 0 ;; 150.0

5 f 100.0

P

U.

a

50.0

INTEC CY-98 Year to Date Airborne Radioactivity Area

‘I

AveragsdZ7Z2sq.ft.

$60.0

240.0

20.0

0.0 95 96 97

827 82.4

76.8 827 - - - - - - I

t 0.0

0 1st Qtr 2nd Qtr

3rd Qtr

Total Aiborne - - - - Permanent

Total Airborne Radioactivity Area at the INTEC at the end of the first quarter was reduced to 82,442 square feet due to grouting at the WCF. 76,822 square feet is designated as permanent and in-use.

5 4

& 20-- 0 n E

15- -

95 96 97

.total Elm


Total Nurrber - - - - - - - Occurrence Report

4th Qtr

.

There were no spills or loss of control of radioactive material during the first quarter.

30

Power Burst Facility

Waste Reduction Operations Complex

Waste Experimental Reduction Facility

(PBFDVROC)

1. Major contributors to the first quarter occupational radiation exposure in the PBFNROC reporting area were working with mixed waste, sizing and compaction of low level waste, incineration, routines, and instrument calibrations.

31

PBFMlROC CY-98 Collective Year to Date Penetrating Radiation Dose


Actual - - - - - - - Goal

PBF/WROC collective penetrating radiation exposure through the end of the first quarter was

2%

E E l - - $ g!

0.1 15 person rem.

b

i s 0 :;Dl 0.90

0.70

050 0.30 1.2 _ - - - - ---.-- 0.W

0.9 _ * - - - - - - m m 97

.---- .- -- - - - 0:w.. . - - - - -

* * - - ..-- -. - * 0.30 .--- - * - - _ - - - - --.--- 0 ---.---- - 072

O r + - :

PBFWROC CY-98 Year to Date Average Worker Dose

0.1

E E

0.04 -.

0.02 -.

95 96 97

0.009

0

0 1st Qtr 2nd Qtr

3rd Qtr 4th Qtr

The PBF/WROC average worker dose through the end of the first quarter was 0.009 rem. Average dose is based on a comparison of workers who receive measurable dose.

32

PBFMlROC CY-98 Year to Date Skin Contaminations

0

10 b-

0

0

m r - C

c

C 0 E 6 5 - 4 2 2 5 2.- 2


-Total Mmber - . - . - - - Occurrence Report

A v o r a w = 1.33 ‘im 95 Df 01

- -

1

4th Qtr

10 ’.

0 - ). m r

s

E 2.-

2 6 - - ’ m c C - 4 0 L 0 P

z

Avoraga = .667

8 - - i F l

0

01 95 96

- -

I



4th Qtr

There was one non-reportable clothing contamination at the PBF/WROC area during the first quarter. An employee’s shoe was contaminated to 200 cpm while changing light bulbs in the PBF reactor building basement.

33

PBFNROC CY-98 Year to Date Airborne Radioactivity Events

5

I - -

0 0

There have been no airborne activity events greater than 10 % DAC detected at the PBF/WROC area through the first quarter.

25

20

5

0 0

PBFNROC CY-98 Year to Date Radioactive Material Intakes

0 0


htakes > IO mrem - - - - - - - Occurrence Report

4th Qtr

There were no positive bioassays indicating radioactive material intakes that resulted in a dose assessment of 10 mrem or greater in the PBF/WROC area during the first quarter.

34

PBFNROC CY-9.8 Year to Date Contamination Area

20,

,5 0 0 0 F

x

U 3 10.-

g v, 5 . -

"mI 4.0

2.0

0.0 s5 96 97

7.38 7.38

7.38 7.38

O J 0 1 st Qtr 2nd Qtr 3rd Qtr

-Total Cont. Area - - - - - - . Rrmanent in use

4th Qtr

The first quarter Contamination Area for the PBF/WROC area remains at 7,378 square feet. All of this is considered permanent and in-use.

6.00

0

r 0" 4.00

x - t

s g 2.00

LI.

to

0.00

PBFMROC CY-98 Year to Date High Contamination Area

95 96 97

2.29 2.29 2.29 2.29

0 1st Qtr 2nd Qtr

Totaltigh - - - - - . - Rrmanent in use

3rd Qtr 4th Qtr

The total High Contamination Area through the end of the first quarter at the PBFNROC area remains at 2,288 square feet. All of this is considered permanent and in use.

35

5.00

4.00

0 0 0 ;; 3.00 U 0 0) U

5 2.00 P

0.00

I PBFNROC CY-98 Year to Date I Airborne Radioactivity Area iml 10 0.5

0.0 95 96 97

200 . 2.00

200 2.00


Total Aiborne - - - - - - - R r m n e n t in use

4th Qtr

The total Airborne Radioactivity Area at PBF/WROC at the end of the first quarter remained at 2000 square feet. All of this area is designated as permanent and in-use.

10

8

6 &

= 4

P

E

2

0

PBFMlROC CY-98 Year to Date Spills


Total Number - . - - . . - Occurrence Report

4th Qtr

There have been no spills at PBF/WROC through the end of the first quarter.

36

Radioactive Waste Management Complex

1. Major contributors to the first quarter RWMC occupational radiation exposure have been from waste disposal, drum handling, assay and inspections, and reconfiguration.

2. The HCA area at the RWMC is under a protective tarp covering the waste stack at the TSA- RE. This area will remain a permanent HCA until retrieval operations begin in that area.

3. Sandia waste boxes in storage modules remain contaminated at the end of the first quarter. These boxes represent the increase in low level contamination shown in the chart on page 39.

37

I RWMC CY-98 Collective Year to Date I Penetrating Radiation Dose 10

. 8

E 6 e! c 0

2 4 2

2

0

I 95 96 97 4

2.5 _...-- __..---- 2.1 -. . - - - *- _ _ _ - - - -



The RWMC collective penetrating radiation exposure through the end of the first quarter was 2.540 person-rem. Dose is up due to increased waste handling operations.

RWMC CY-98 Year to Date Average Worker Dose

0.25

0.1 - -

0.046 0.05 - -


The average worker dose at the RWMC through the end of the first quarter was 0.046 rem fiom 55 workers who received dose.

38

0

RWMC CY-98 Year to Date Skin Contaminations

95 96 97

3 0



4th Qtr

RWMC year to date skin contaminations remain at zero through the end of the first quarter.

0

RWMC CY-98 Year to Date Clothing contaminations :rl 95 96

0 0



4th Qtr

There were no clothing contaminations at the RWMC through the end of the CY-98 first quarter.

39

5

4

1

0

RWMC CY-98 Year To Date Airborne Radioactivity Events

4

l r l 0 I

95 96 97

I 0


No airborne activity greater than 10 % DAC was detected at RWMC in areas not posted as Airborne Radioactivi& Areas through the first quarter.

RWMC CY-98 Year to Date Radioactive Material Intakes

5

4

v)

r r

w g 3 c

L. 0

$ 2

5 z 1

0

0

Avg.=33

95 96 97

1 0

1st Qtr 2nd Qtr

Intakes >10 mrem - - - - - - - Occurrence Report

3rd Qtr 4th Qtr

In the last quarter of 1996, final analysis of one positive bioassay indicated an uptake of 43 mrem CEDE as shown on the chart. There have been no positive bioassays year to date indicating an intake of radioactive material that resulted in a dose assessment of 10 mrem or greater.

40

20*-

0 0

15.-

P c

1st Qtr 2nd Qtr 3rd Qtr Total Cont. Area - - - - - - - Permanent in u s e

10

8

6

4

0 95 96 97

4th Qtr

0.0 7

The total Contamination Area at the RWMC through the end of the first quarter increased to 10,240 square feet due to contaminated Sandia waste boxes in storage containers at the RWMC.

0.0 95 96 97

29.5 29.5

29.5 29.5

I RWMC CY-98 High Contamination Area I

60.0 0 0 0 P

x

1L

L.

% 40.0

a $ 20.0

0 1st Qtr 2nd Qtr

Total Hgh - - . . - - - Permanent in use

3rd Qtr 4th Qtr

The total High Contamination Area at the RWMC through the end of the first quarter was 29,525 square feet. All of this area is designated as permanent and in-use.

41

RWMC CY-98 Airborne Radioactivity Area 500

400

5300

s U

3

v) 200

0 0 0


Total Airborne - - - - - - - Permanent in use

4th Qtr

The total Airborne Radioactivity Area at the RWMC at the end of the first quarter remains at zero square feet.

25

20

15 a n

5 = 10

5

0

I RWMC CY-98 Year to Date Spills I

91

0 0 7



4th Qtr

There were no spills or loss of control of radioactive material during the first quarter at the RWMC.

42

Test Reactor Area

1. Outages at the Advance Test Reactor within the Test Reactor Area are responsible for the major portions of dose during the first quarter. Total Penetrating dose for the report is 2.954 person-rem year to date.

2. Two contamination events occurred at TRA. They were not reportable events. The first was a shoe contamination from building 605, the second involved pants and shoes fiom an individual testing the air connection to the tank for back flush of the Hot Waste System.

43

30

25

20 E t 6 15

10 0

5

0

- - .- 96 97 126- * -- - 95

-- - - ..-" 6.3-. - - --. .-- .-- _.--

I TRA CY-98 Collective Year to Date I Penetrating Radiation Dose

0 1st Qtr 2nd Qtr

Act=[ - -. . . . . Goal

3rd Qtr 4th Qtr

TRA collective penetrating radiation dose through the end of the first quarter was 2.594 person- rem.

E e!

0.25

TRA CY-98 Average Year To Date Worker Dose

1 02w 1 Aversge=O.O78rem

95 96 97

0.05 O-l t 0.03

0 0 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr

The average worker dose at the TRA through the end of the first quarter was 0.027 rem based on 108 workers with dose greater than 10 mrem.

44

25

g 20

z

s

0

IZ 15

C C

10

ti E = 5 z

.a

0

- TRA CY-98 Year to Date

Skin Contaminations

There were no skin contaminations at the TRA during the first quarter. There were no contaminated wounds or facial contaminations.

* -

TRACY-98 Year to Date Clothing Contaminations

35

-I - : : : : L A ORAvaago.S.3

M.0

_ _ 5.0

0.0 85 96 97

0 0 0 .?

0

5 a l o - - E a = 5 . -

- .

0

2 0

o<: 1st Qtr 2nd Qtr 3rd Qtr

-Total - - - - . - - Occurrence Report

4th Qtr

There were two clothing contaminations at the TRA during the first quarter. They did not meet recordable criteria.

45

5

4

I

0

TRA CY-98 Year to Date Airborne Radioactivity Events


No airborne activity greater than 10 % DAC was detected at the TRA in areas not already posted as Airborne Radioactivity Areas during the first quarter.

20

TRA CY-98 Year to Date Radioactive Material Intakes

1

15 In a x m w E I

10 L. a n E a

5 z


Intakes >IO mrem . . . . - - - Occurrence Report

4th Qtr

--

There were no positive bioassays indicating an intake of radioactive material that resulted in a dose assessment of 10 mrem or greater at the TRA during the first quarter.

46

150.0

TRA CY-98 Year to Date Contamination Area

0 0

r 0 100.0 x * 0 PI U

E P a 50.0

' 20 40w 0

45 95 97

49.7 50.0

125.6 ' 25.6

0.0 4 0 3rd Qtr 1st Qtr 2nd

Qtr Total Cont. Area - - - - - - - krmanent in u s e

4th Qtr

Total indoor Contamination Area for the TRA is 49,978 square feet square feet. 25,619 square feet is designated as permanent and in-use,

TRA CY-98 Year to Date High Contamination Area

10.0

2.0

0.0 0

20 ----..-.-.

1.4

26

30- - - - -


Total Hgh - - - - - - - krmanent in use

4th Qtr

Total High Contamination Area for the TRA at the end of the first quarter has reduced to 2,025 square feet. 1,400 square feet of this area is designated as permanent and in-use. The chart shows rounded values.

47

TRA CY-98 Year to Date Airborne Radioactivity Area

5,000 - *

0 0 0 0 1st Qtr 2nd 3rd Qtr

Qtr Total Airborne - - - - - - - Rrmanent in use

4th Qtr

Total Airborne Radioactivity Area at the TRA at the end of the first quarter remains at zero square feet.

20

15

5

0 0

ORAvaage=l.67 :m 5 0

95 96 97


Total Mmber - - - - -. Occurrence Report

4th Qtr

There was one non-reportable spill or loss of control of radioactive material at the TRA during the first quarter. This was associated with the Hot Waste system.

48

I

MAC-ISOTOPES

TRA HOT CELL

summary

The TRA Hot Cell (MAC-I) is a privatized contractor and is being tracked here since LMITCO provides much of the associated labor support.

Activities include isotope separation work and associated source activities. The data on the following pages is not added to LMITCO totals.

International Isotopes Inc., of Denton, Texas acquired MAC-I on April 27, 1998. MAC-I will be known as International Isotopes Idaho Inc. (IIII) in future reports.

49

10

8

6

4

2

0 0

I MAC4 CY-98 Collective Year to Date I Penetrating Radiation Dose

95 96 97

5.9


Actual - - - . . . . Goal

Year to date dose is 0.834 person-rem

0.25

0.2

0.15

E g!

0.1

0.05

0

I MAC4 CY-98 Average Year To Date Worker Dose

4th Qtr

0200

0.w)

0.m

0.050

0.000

95 96 97

0.06

0 1st Qtr 2nd Qtr

Average year to date is 0.06 rem

3rd Qtr 4th Qtr

--

I

50

MAC-I CY-98 Year to Date Skin Contaminations

25 I

5.0 j 0.0 : '0.0 : ;e 0.0

95 96 97

0 0 0 0


-Total Number - - - - - - - Occurrence Report

There have been no skin contamination events at the Hot Cell facility year to date. The average is based on an event at the beginning of CY-97

35

30

= 25

u) r 0

B c

% Y 20 c 0

0 15

2 10 E = 5

a

I.

MAC-I CY-98 Year to Date Clothing Contaminations

95 96 97

I 0


-Total . - - - - - - Occurrence Report

MAC-I has had no reportable clothing contamination events year to date.

4th Qtr

51

MAC-I CY-98 Year to Date Airborne Radioactivity Events

4 -

v)

c

w 0 0)

L

f 3 - c

L

2 - 5 z

Avg.nclddlned

to 95 96 97

0

0 . 1st Qtr 2nd Qtr

There have been no events greater than 10% DAC year to date.

3rd Qtr 4th Qtr

MAC-I CY-98 Year to Date Radioactive Material Intakes


Intakes >IO mrem - - - - - - - Occurrence Report

There have been no internal doses confirmed from MAC-I operations year to date.

4th Qtr

52

5

4

8

x 3.- 0 r

Y Q al L

i! 2-- J u- fn

1

MAC4 CY-98 Year to Date Contamination Area

1 .-

*r

L

MAC-ICY-98 Year to Date High Contamination Area

95

Y Q Q L

f 4.0

2.0 3

96

- -

- -

97

95 96 97

0.834

0 1 st Qtr 2nd Qtr 3rd Qtr Total a n t . Area - - - - - - - F’ermnent in use

4th Qtr

Contamination areas total 834 square feet at the Hot Cell at TRA

0.7 0.0

0.0 0 1st Qtr 2nd Qtr 3rd Qtr

Total Hgh - - - - - - - krmanent in use

4th Qtr

Trending data is just being established for MAC-I. Year to date High Contamination is 680 square feet.

53

0

a 2

5

MAC-I CY-98 Airborne Radioactivity Area I

- -

95 96 97

1st Qtr 2nd 3rd Qtr Qtr

Total Airborne - - - - - - - Wrmanent in use

There has been no Airborne events year to date at the MAC-I.

4th Qtr

20

85 96 97

0 0 0


Total kmber - - - - - - - Occurrence Report

4th Qtr

--

No Spills have occurred at MAC-I year to date.

54

Test Area North &

Specific Manufacturing Capability

1. TAN hot shop work, handling repackaging, and shipment of hot waste, cask disassembly, ER remediation activities, and pool cleaning and vacuuming account for dose at TAN Ops. For SMC, routine armor manufacturing and routine activities account for the dose contribution.

2. One event at TAN 666 created contamination spread resulting in an OR (ID-LITC-TANO- 1998-001). One of the tanks had a back-flow problem causing liquid to come up through floor drains,

55

10

8

€ 6 ! g 4

S 0

n

2

0

Averam = 7.582 ran

6.5 5 ..--- 0 5.0-,. - * -

.-- - - - - - - -.--

95 96 97 ---.---- 3.4 .- - - - -- -

- - * - .*---

:I id

TAN/SMC CY-98 Year to Date Average Worker Dose



0.25 2-

4th Qtr

TAN and SMC collective penetrating radiation dose through the end of the first quarter was 1.244 person-rem. Work scope is consistent with that of past years.

0.05 0.028

0 0 2nd

Qtr 1st Qtr 3rd Qtr 4th Qtr

The average worker dose at the TAN/SMC through the end of the first quarter was 0.028 rem based on 44 workers who received dose greater than 10 mrem.

56

20

v) r

m c e 15

E 5 10 m L

0 0

0) P

z

c

L

E 5 a

0

TAN/SMC CY-97 Year to Date Clothing Contaminations

TAN/SMC CY-98 Year to Date Skin Contaminations

20,

1 0


-Total Number - - - - - - . Occurrence Report

4th Qtr

There were no skin contaminations at TAN/SMC during the first quarter. There were no facial or wound contaminations during the quarter.

l'-

0 0



4th Qtr

There was no contamination on company clothing that occurred at TAN/SMC during the first quarter.

57

5

1

1

:: irl 0 1

94 95 97

0 0 0

TANlSMC CY-98 Year to Date Radioactive Material Intakes

I TAN/SMC CY-97 Year to Date I Airborne Radioactivity Events

4

2

16

Q

a - _ 4

0 95 96 97

- -


No airborne activity event greater than 10 % DAC was detected at TAN/SMC in areas not posted as Airborne Radioactivity Areas during the first quarter.

0 0 0


htakes > IO rmem - - - - - - - Occurrence Report

No internal uptakes occurred at TAN/SMC during the first quarter. There are still 22 analyses unresolved at this time.

58

150.0

CI w U r z 100.0

z I!

a 0

L

a 50.0

m

8

0.0

TAN/SMC CY-98 Year to Date Contamination Area

84

m 96 97

53.2 53.2

52.9 52.9


Total Cont. Area - - - - - - - Wrmanent in use

4th Qtr

The total Contamination Area at TAN/SMC at the end of the first quarter was 53,226 square feet. 52,926 square feet was designated as permanent and in-use. A 400 square foot area was

decontaminated at the SMC during the second quarter.

TAN/SMC CY-98 High Contamination Area

50.0 1

0 40.0 U E m u)

g 30.0 B Y

""IIIII 5.0 0.0

95 95 97

2 20.0

m a

0.0 -I 0 1st Qtr 2nd Qtr 3rd Qtr

Total Kgh - - - - - - - Wrmanent in use

4th Qtr

The total High Contamination Area at TAN/SMC at the end of the first quarter remains constant at 11,526 square feet. All of this area is designated as permanent and in-use.

59

TAN/SMC CY-98 Airborne Radioactivity Area

L al .n E a

2--

95 86 97

Avaape 4 6 7

4 : : : r l 3 2 4

0

95 96 97

1

0 0 0


Total Airborne . - - - - - - Wrmanent in use

4th Qtr

Total Airborne Radioactivity Area at TAN/SMC remains at zero through the end of the first quarter.

I

Y I

.- I



4th Qtr

One spill occurred at TAN 666 as a result of back-flow from the number three holding tank up through floor sumps. Decontamination of the area is in progress.

60

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