ML20149F886
| ML20149F886 | |
| Person / Time | |
|---|---|
| Site: | Framatome ANP Richland |
| Issue date: | 10/22/1991 |
| From: | Feuerbacher R, Malody C, Probasco T SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| To: | |
| Shared Package | |
| ML19304C543 | List: |
| References | |
| EMF-91-198, NUDOCS 9409280090 | |
| Download: ML20149F886 (23) | |
Text
_____
l Siemens Nuclear Power Corporation l
EMF-91-198 l
October 1991 Issue Date:
10/22/91 1990 ALARA COMMITTEE REPORT R. L Feuerbacher E. L Foster J. W. Helton D. C. Kilian C. W. Malody R. B. McLees T. C. Probasco W. E. Stavig l
l l
/Of2f 4 Concur:
/
~
T. C. Probasco, Health Physics
( Dale Safety D./5$
M-3/-9/
E. L. Foster, Radiation Safety Officer Date Safety Approve:
M
/d-Z/- 9/
C. W. Malody, Manager
(/
Date Regulatory Compliance (Chairman) cip
- z N.[2ggo 7
EMF-91-198 October 1991 Page 1 1990 ALARA COMMITTEE REPORT
1.0 INTRODUCTION
This report for calencer year 1990 is submitted to the industrial Health and Safety Council in accordance with the requirements of License SNM-1227. The objectives of this report are to:
l l
1.
Determine trends in personnel exposure and effluent releases.
l l
2.
Determine if existing equipment and procedures for radioactive effluent and exposure control are being properly used, maintained and inspected.
l l
3.
Determine if personnel exposure or radioactive effluents might be reduced under the concept of as low as reasonably achievable (ALARA).
The above objectives are accomplished by review of employee external and internal exposure data, unusual occurrence reports, effluent / environmental data and plant environmental trends.
l l
l 1
l 1
i-
EMF-91-198 October 1991 Page 2 2.0
SUMMARY
1.
There was an uptrend of significance in the uranium to sewer releases (Table 11) which resulted from the addition of spent incinerator scrub solution to Lagoon 5A, the inclusion of small amounts of LUR waste in the feed to ARF and higher production rates in conversion. These higher uranium discards to sewer caused the uranium concentration in the Rhhland sewage treatment plant sludge to approach the limit of 25 pCi per gram.
This has been brought back under control by discontinuing feeding LUR waste to ARF and SWUR scrubber solution to Lagoon SA until an ion exchange system is installed in the Lagoon SA discard stream to sewer.
2.
There was an upward movement in whole body exposure of the uranium work force (Table IV) due to a larger work force and a significant increase in production. It is not expected that this is the beginning of an uptrend but that these higher levels may persist based upon production forecasts. There was a decrease for fuel performance.
3.
Average air concentrations appear to be within experience levels for uranium operations (Table IV) and are significantly below even the new 10 CFR limits of 2x10-11 by a factor of 5. It is interesting to note that the downtrend in NAF (Figure 3) which was first noted in last years report continues. Figure 4 indicates an uptrend in Line 2 air concentrations which as been resolved by appropriate hood installation.
4.
The average of positive lung counts remained near past averages however the totallung dose has increased. This is due to a larger number of employees counted then previous years but primarily due to the fact that Battelle equipment and counting techniques have improved resulting in lower detection levels which in turn results in more positive counts.
5.
The number of urine samples better than doubled during 1990 over previous years. Early in 1990 it was determined that the sample schedule and uranium concentration limit in use for urinalysis control was not adequate to monitor for chemical toxicity. Immediate
EMF-91-198 October 1991 Page 3 i
corrective action was to increase the sample schedule from monthly to every two weeks and to drive the sensitivity of the analyses down to the point where a violation of toxicity limits could be more easily determined. New action levels were established internally on the basis of toxicity. Early in 1991 following one years experience with the new program, the bioassay program was again revised within existing license limits. A license amendment will be submitted to formalize a bioassay program which is different from that allowed by the license and more in line with recommendations in Reg. Guide 8.11.
6.
Twelve Health Physics audits were conducted during the year containing a total of six findings. Five of six items were closed by year end. The one open item remaining is to reduce contamination releases from the Vac-U-Max system. Engineering has the system under evaluation.
EMF-91-198 October 1991 Page 4 3.0 ALARA PROJECTS CHEMICAL AREA COMPLETED 1.
A new station for cutting and packaging contaminated HEPA filters was started up.
2.
The hood on Line 1 of the U 0 facility was rebuilt to improve containment and correct 33 leaks.
3.
Additional filters were added to protect vacuum transfer diverter valves from damage by powder. Failure of these valves causes airborne contamination from the vacuum transfer system during operation plus additional contamination during maintenance of the valve.
4.
Filter canisters at each vacuum transfer pump were reoriented to vertical to reduce powder release during filter changes.
5.
The powder bottle loading station for filling containers for powder shipment was brought to operational status.
6.
Bridge breakers on the Une 1 calciner feed hopper were removed. Powder leaks from failed seals contributed to airborne contamination.
7.
Doors on many of the powder prep hoods were upgraded with thicker material to reduce warpage and improve seals.
8.
A high DP alarm was added to the Une 1 POG system to alert the operators that the HEPA filters require replacement before vacuum is lost on the system.
9.
A new scrubber for the ELO Gd SX system was constructed and put into service.
EMF-91-198 October 1991
~D.
Page 5 PROJECTS IN PROGRESS A new klinker bucket elevator will be installed on the second U 0 line. Materialis on 3 8 1.
hand but production schedules have prevented installation.
2.
Long term development of UF scrubbing technique is planned but has received low 3
priority. This will apply to controlling UF releases and purge gases from the hydrolysis s
system.
Design of the solid waste sorting station has been completed. An AR for funding is being 3.
prepared.
A portable thickness gage for inspection of metal powder transfer piping was purchased 4.
and is being tested. The instrument will be used to detect erosion of the piping to allow replacement prior to breaching of the pipe.
NEW PROJECTS 1.
A new hood design for use on contaminated equipment is being implemented, it will improve the seal on the hood panels and reduce pockets of contamination within the hood.
2.
A new hood will be added at the Une 1 blender discharge to improve containment during enrichment cleanout.
3.
A central vacuum system will be installed in the Une 1 blend room to improve cleanup.
4.
Heavier gauge walls and stronger clamps will be used in the hoppers below each granulator to reduce powder in the hoods. This has been completed on Une 1.
Implementation on Unes 2 and 3 will occur when the hoppers reach end-of-life.
EMF-91-198 October 1991 Page 6 5.
Extension of the roll compactor hoods on Lines 2 and 3 is planned to enclose the hopper feeding the roll compactor. This will improve containment during ECO's. Design of the b
hoods is complete and installation is expected soon.
6.
A new enclosure for the Line 3 powder hopper filters is planned. This will improve containment during filter changes. Design is complete and materials are on order. If successful on this line, implementation on the other lines will be evaluated.
7.
The ash receiver hood below the SWUR hammermill is being modified to provide containment for ash sampling and ash transfer operations.
8.
The SWUR off gas system is being modified to improve control and efficiency. This will i
reduce puffing material into the room and reduce exposure due to changing HEPA filters.
9.
An action plan to reduce ammonia fumes in the conversion area is being implemented.
Sines the ammonia is associated with fissile material processing, a reduction in airborne radioactivity is also expected.
CANCELED PROJECTS 1.
A level switch to be installed in the drop chute of the Une 2 calciner to detect plugging in the discharge was. canceled when no suitable level switch for this application could be identified.
2.
Venting of the Hopper 3 dump valve was canceled when administrative controls eliminated problems of bellows failure.
e
EMF-91-198 October 1991 Page 7 P
CERAMIC AREA COMPLETED 1.
A press tooling and cleaning station in the UO Pelletizing area was completed.
2 2.
The Une 1 press was repaired to improve hood containment and reduce vibrations which assists contamination escape.
3.
The central vac systems in Room 100,182, and U 0 were upgraded for better suction 38 thus reducing loose powder problems.
PROJECT IN PROGRESS 1.
A new boat loading system will be installed in combination with the new Line 4 press.
One-piece boats used with the system will reduce contamination in boat storage and handling areas. The system is scheduled to be operational yet this year. Replacement of the other stackers will follow in subsequent years.
2.
A press tooling station for NAF will be evaluated.
3.
A ventilated hood for maintenance work on grinder assemblies will be evaluated.
NEW PROJECTS 1.
The bucket seal at the Scrap Pellet Hood near the grinders will be upgraded to improve containment. Materials are on hand but production schedules prevent installation.
2.
Scales will be added under the scrap pellet buckets at each inspection station. These will reduce handling and resultant airborne contamination.
EMF-91-198 October 1991 Page 8 3.
Upgrades to the grinder water systems are being evaluated to reduce loose powder on the ground pellet surfaces. This will reduce airborne contamination in subsequent handling.
4.
Planning has begun on a NAF furnace to eliminate problems of transport of loaded boats and the resultant contamination from extra handling.
l e
______-___.___.m___
TABLES
EMF-91-198 October 1991 Page 10 TABLE I EFFLUENTS RADIOACTIVE MATERIAL' Gaseous Effluent to Liquid Effluent to City Year the Atmosphere (pCI)
Sewer System (Cl) Uranium U
FP Sewer Data Lagoon Data 1988
<20.2
< 2.5
<0.068 0.017 l
1989
< 15.7
< 4.8
<0.061 0.040 1990
< 17.1
< 0.9
<0.052 0.064 l
1 The value of the detection limit is included where the constituent was present at levels below the minimum detection capabilities of the measuring equipment.
... _ ~... -
EMF-91-198 October 1991 Page 11 TABLE Il SEWAGE TREATMENT Pl. ANT SLUDGE' (PCilg)*
1988 1989 1990 JANUARY 4.8 11.7 7.7 FEBRUARY 9.0 11.2 6.5 MARCH 6.3 10.9 6.9 APRIL 8.7 13.5 3.4 MAY 10.7 14.0 7.0 JUNE 10.0 10.8 16.0 JULY 7.2 12.7 11.9 AUGUST 7.7 12.7 18.3 SEPTEMBER 16.2 9.2 24.7 OCTOBER 6.9 13.5 23.3 NOVEMBER 12.5 13.3 20.1 DECEMBER 9.0 13.6 10.0 MAX / MUM 16.2 14.0 24.7 AVERAGE 9.08 12.3 15.6 LIMIT 25.0 average for six consecutive months 30.0 single sample 1
Sludge measured in damp form as removed from treatment plant.
2 Three weight percent enriched uranium assumed when not analyzed for isotopic content.
The original analysis data is in pg U/g of sample (ppm).
EMF-91-198 October 1991 Page 12 TABLE Ill EXTERNAL WHOLE BODY EXPOSURE Avg. Exposure Total Man-Rem No. of Persons Organization (mrem) 88 89 90 88 89 90 88 89 90 Plant Operations 149 151 166 74 80 141 11.08 12.12 23.48 Maintenance 68 65 78 29 17 22 1.96 1.08 1.73 i
All Others 141 161 195 27 20 26 3.77 3.29 5.06 Subtotal 358 377 439 47 44 69 1 6.81 16.49 30.27 fuel Performance 26 29 29 199 79 110 5.18 2.30 3.20 Grand Total 384 406 468 57 46 72 21.99 18.79 33.47 2
Reactor Exposure 48 45 55 153 56 67 7.6 2.50 3.66 0.25-0.50 Rem 0.50-0.75 Rem 0.75-1.0 Rem
>1.0 Rem O
om 1988 4
1 0
0 1989 4
1 0
0 1990 28 2
0 0
3 Fuel Performance 0.25-0.50 Rem 0.50-0.75 Rem 0.75-1.0 Rem
>1.0 Rem l
1988 4
2 0
1 1989 3
0 0
0 i
1990 3
2 0
0 l
1 Other production-related personnel such as 0C, rod loading, lab personnel, and some engineering groups.
2 Exposure obtained during reactor site work by both Fuel Performance and non-Fuel Performance ANF personnel not on the ANF dosimeter.
3 On-site exposure only.
g4 EMF-91-198 October 1991 Page 13 TABLE IV AIRBORNE RADIONUCLIDE CONCENTRATION DATA 1
2 Average Concentration Calculated Average Lung (1 0'11 pCl/mt)
Dose (Rems / Person)
Area 1988 1989 1990 1988 1989 1990 3
Line 1 0.38 0.40 0.49 0.57 0.60 0.74 4
Line 2 0.64 0.43 0.65 0.96 0.64 0.98 Press 0.67 0.54 0.51 1.01 0.81 0.77 Grinder 0.52 0.40 0.43 0.78 0.60 0.65 UO 0.45 0.44 0.56 0.68 0.66 0.84 3 g Lube Blend 0.57 0.30 0.38 0.86 0.45 0.57 Scrap Recovery 0.37 0.23 0.25 0.56 0.35 0.38 Powder Storage 0.33 0.31 0.47 0.50 0.46 0.71 NAF 0.57 0.35 0.28 0.86 0.53 0.42 SWUR 0.21 0.26 0.31 0.39 Average Uranium Operations 0.50 0.38 0.43 0.75 0.57 0.65 Fuel Performance 2.50 0.59 0.44 0.38 0.09 0.07 5
Uranium Operations Rems / Person Persons Man-Rem 1988 0.75 207 155 7989 0.57 202 115 1990 0.65 239 155 l
l 1
This average is not a function of worker occupancy of the area, nor does it allow for respiratory usage.
2 Based on ICRP ll, assumes continuous intake of insoluble material for 2,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> over one year.
3 Average of Une 1 conversion and powder preparation.
4 Average of Line 2 conversion, powder preparation, and off-line powder preparation.
5 Data taken from Table VI and not a function of area occupancy or respiratory protection.
l i
E] $o>
7 0
8 1
0 0
3 3
8 8
O@{ $-
1 7
9 6
4 1
5 2
6 6
yu* ma 2
1 esoD) 6 1
3 0
0 1
4 6
gm 9
le 0
8 1
9 ne 8
3 e
v uR 2
1 L(
L sp a
n )5 u
l o
1 4
6 1
i3 o
to r
t 2 g
1 3
1 6
c g
T 8
n 8
0 8
4 2
AU i
g 3
1 5
w n
6 5
o el 1
vC 1
l i r on l
e o
f e
b 6 n
8 0
0 3
3 2
A s
ig 2
3 7
1 y
0 0
1 1
0 1
e (0 r
a n
a 1
d e
9 0
0 0
0 e
0 b
5 e
M m
6 e )5 u
3 mo 6
4 N
e iv3 7
1 s
2 0
6 7
2 h
t i
t d
0 1
s 9
1 1
oU 8
0 0
0 0
g n
C i
a n
)
m u
l, r
f A
o (n e
e d
n T
5 6
1 6
R g
n A
g 6
8 1
6
(
n o
v 8
D A
8 1
1 1
1 e
u s
T 0
0 0
0 s
2 1
1 l
e r
o 5
4 4
e p
N D
h U
b t
O g
o la n
t C
s 0
5 0
1 5
1 u
m g
e 9
3 L
1 1
G e
e in r
N ye d
ov 5
a U
lpi 9
0 6
0 1
7 i
1 t
o L
8 1
1 t
s l
ms n
e d
6 o
e d
o V
E.P m
iv r
E o
8 e) o 6
2 0
9 C
L N
8 r5 1
r B
u3 p
1 1
O A
s2 8
2 2
i s
e a -
f T
eU 2
2 2
l a
0 6
2 7
2 7
Mi 0
0 0
la h
f 6
6 5
0 8
C c
t h
s 9
1 2
sn u
e e(
e s
e oe ig iv l
yd h
t e
c n
t lpn 9
7 3
8 7
5 H
e n
f o
mu 8
5 4
5 8
4 fe s
o 2
E y
r
.C a
e o
d p
N 8
4 9
7 8
8 0
d 8
5 3
5 6
1 0
e 2
5 le ta a
r r
8 9
0 ht a
8 8
9 in n
t e
9 9
9 we io Y
1 1
1 5 m tc n
s 3e u
o n
2u d
a r
i p
s Us o
ta O
n e
r e
i a p
z g
Ce p
c i
n 2
a nm e
r na o
O n
s r
1
- 8. h i
a r
e e
h g
s c
n e
v t
O e
m e
h A
0t O
r r
i t
t
/
v a
n O
a l
n r
i t
o e
a l
1 2
o l
C C
M A
T l
l l
EMF-91-198 October 1991 Page 15 4
TABLE VI URINALYSIS DATA Ho. of Persons No. of Samples >
ido, of Samples Organization Sampled 10 pg U/t 88 89 90 88 89 90 88 89 90 Conversion Opns 55 37 63 574 348 1280 8
1 3
Ceramic Opns 43 59 58 376 551 963 3
0 0
Maintenance 62 54 54 635 604 1217 1
1 0
i All Others 47 52 64 238 263 466 3
0 0
Total 207 202 239 1823 1766 3926 15 2
3 Number Ab
^ '"
Year Highest Sample (pg U/t) j0 pg U )
1988 53.1 15 1989 14.5 2
1990 19.2 3
1 Other production-related personnel such as OC, rod loading, lab personnel, and some engineering groups.
M FIGURES
\\
t.
1 O.9 U
LhE2 k
0.8 0.7 0.6 id N
TN l;l f
\\,/ \\\\ h N
,0.3 y
gg n
1/87 3/87 1/88 3/88 1/89 3/89 1/90 3/90 2/87 4/87 2/88 4/88 2/89 4/89 2/90 4/90 Quarter / Year l
l
Ceramics-1 PRESSES 0.9 a
j GRNDERS N
g 0.8 y a, N N
/\\
/
J\\
/e \\
s se 7
W /\\ V\\
as
\\
a v
v <
0A
(
un a
e 0.3 gg 555 1/87 3/87 1/88 3/88 1/89 3/89 1/90 3/90 2/87 4/87 2/88 4/88 2/89 4/89 2/90 QuarterNear f
j l
NAF-Air 1
\\
n 0.9 3
\\ / \\
g DB
(
e 3
0.7 sk k
O.6 y
l 0.5 0.4 l
\\ !
\\
0.3 V
N di 4
O.2 iss 1/87 3/87 1/88 3/88 1/89 3/89 1/90 3/90 2/87 4/87 2/88 4/88 2/89 4/89 2/90 4/90 Quarter / Year I
e s
Fi0ure4 Powder Prep-Air Concentradons 1
/
Ye1 0.9 a
UNE2
}
w
/D R X u
\\
~
/
ah
/ /
W
- l NY v
1/89 3/89 1/90 3/90 I
2/89 4/89 2/90 4/90 f
QuarterNear b
EMF-91-198 October 1991 Issue Date:
10/22/91 1990 ALARA COMMITTEE REPORT Distribution T. A.Bjornard R. E.Collingham J. B. Edgar B. N.Femreite R. LFeuerbacher E. L. Foster R. G.Frain S. F.Gaines J. W.Helton D. J. Hill W. V. Jackson B. H.Kalthoff D. C.Kilian M. A. Law S. R.Lockhaven C. W.Malody C. D. Manning G. B.Mathison R. B.McLees J. N. Morgan T. C.Probasco A. Reparaz G. LRitter I. J.Samaritano W. E.Stavig M. K. Valentine C. J.Volmer M. D. Weiss D. D. Whitlow H. E.Williamson W. E.Wynn Document Control (5)
__________________________________________________________8__
_