ML17285A449
| ML17285A449 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 04/24/1989 |
| From: | WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | |
| Shared Package | |
| ML17285A431 | List: |
| References | |
| NUDOCS 8905090289 | |
| Download: ML17285A449 (26) | |
Text
WNP-2 APPLICATION FOR APPROVAL TO DISPOSE OF VERY LOW-LEVEL RADIOACTIVE WASTE 1.0
~Por, ose In accordance with 10 CFR 20.302(a);
the Washington Public Power. Supply System requests NRC approval for the proposed disposal of eight contaminated Moisture Separator Reheater.
(NSR) tube bundles with associated assemblies and four small spools of piping with estimated waste volumes of 7400 and 370 cubic feet; respectively.
This application addresses the specific information requested in 10 CFR 20.302(a).
2.0 Waste Descri tion 2.1 Contaminated Moisture Separator Reheater Assemblies During the refueling/maintenance outage in the Spring of 1987, the Supply System replaced eight MSR tube bundles including tube
- sheets, hemispherical heads and associated components.
These bundles were replaced because of possible design inadequacies resulting in erosion and poor performance.
The NSR tube assemblies, being on the steam side of a Boiling Mater Reactor, have low levels of radioactive contamination.
Moisture separ ator reheaters ar e important components of the main steam and turbine systems at WNP-2.
They mechanically remove excess moisture from the high pressure turbine exhaust steam and then reheat the dried steam prior to passing the steam on to the low pressure turbines.
This drying and reheating process minimizes erosion of the low pressure turbines caused by excessive moisture and increases the overall efficiency of the low pressure turbines.
MNP-2 employs two MSRs, one on each side of the turbine on the 501-foot elevation of the Turbine Building.
Each MSR consists of an outer shell, moisture separator, chevr ons and four tube bundles (one high pressure and one low pressure at each end).
Each NSR tube bundle is comprised of a large number of 3/4 inch carbon steel U-tubes; roller expanded at each end into a single tube.
The physical dimensions of the tube bundle, including hemispherical head; are approximately 4.5 feet in diameter and 43 feet in length.
The drawing of a typical NSR tube bundle is shown in Figure 1.
Radiological survey data of the MSR tube bundles are shown in Table l.
External exposure rates ranged from background for half of the bundles to 20 mR/hr near the hemispherical head of two of the bundles.
External.
smear surveys taken on the tubes, showed contamination levels ranging from
<1,000 dpm/100 cm2 to 3;000 dpm/100 cm2.
Internal exposure
- rates, measured near the center. of the MSR hemispherical heads,'anged from <O.l mR/hr to 12 mR/hr..
The average internal exposure rate was 3.7 mR/hr.
Internal smear..
survey results ranged from <1,000 dpm/100 cm2 to 300;000 dpm/100 cm2 on one tube sheet.
The average internal smearable contamination level was estimated to be 78;000 dpm/100 cm2.
8905090289 890424 PDR ADOCK 05000397 P
The estimated radioactivity of the MSR tube assemblies is shown below as a
function of r adionuclide and concentration.
Total radioactivity'estimates were based on exposure rate measurements taken near the center of the hemispherical heads; germanium analysis of MSR tube pieces, and the amount of contaminated surface area.
Moisture separator reheater data and radioactivity content calculations are shown in Table 2.
A gamma ray spectrometry analysis of an internal smear. is shown in Table 3.
ESTIMATED RADIONUCLIDE CONTENT OF MSR TUBE ASSEMBLIES Avg Avg Radionuclide Half-life(yrs)
Distribution(X)
Concentration(pCi/gm)
Mn-54 Co-60 Zn-65 0.857 5.27 0.67 1.5 50 48.5 3
100 97 2.2 Contaminated Pipe Spools Du< ing the refueling outage in the Spring of 1987; the Supply System removed four spools of carbon steel piping from the 471-foot elevation of the Turbine Building.
These spools of pipe, located in the steam side of the plant, were removed so that pr eseparators could be installed between the high pr essure turbine and the MSRs.
The overall dimensions of a pipe spool are about 6 ft in length and just over 3 ft in diameter,.
Radiological survey data of the pipe spools are shown in Table 4.
The pipes were not externally contaminated and had background external exposure rates.
Internal exposure
- rates, measured near the center of the
- pipes, ranged from 0.25 mR/hr to 0.6 mR/hr.
The average internal exposure rate was 0.41 mR/hr.
Internal smearable contamination levels were <1;000 dpm/100 cm2 on two of the pipes and up to 3,000 dpm/100 cm2 on the other two pipes.
Radioactivity levels of the pipe spools are shown below as a function of radionuclide and concentration.
Total radioactivity estimates were based on exposure rate measurements taken in the center, of the pipe spools.
A gamma ray spectrometry analysis of an internal smear is shown in Table 5.
Pipe spool data and radioactivity content calculations are shown in Table 6.
ESTIMATED RADIONUCLIDE CONTENT OF PIPE SPOOLS Radionucl ide Half-Life(yr s)
Avg Distribution(X)
Avg Concentration(pCi/gm)
Mn-54 Co-60 Zn 65 Sb"125 0.857 5.27 0.67 2.76 3.5 35 61 0.5 10 102 177 1.5
3.0 Pro osed Dis osal Method 3.1 Disposal Site Location and Description The proposed disposal site is within the WNP-2 controlled area on pr oper ty leased by the Supply System from the US Department of Energy.
Disposal would occur at the refuse landfill located just southwest of the cooling towers and inside the plant perimeter fence (see Figure 2).
This landfill has been used for disposal of construction debris since
- 1976, although usage has become infrequent since completion of construction in 1984.
Figure 3
shows the location relative to access
- routes, site ar ea facilities, and the Columbia River.
The surface soils in the ar ea of the landfill consist of reworked sands and gravels.
Soils and foundation investigations prior to plant constr uction show that the site is underlain with approximately 45 ft (down to approximately 395 ft MSL) of glaciofluvial sediments (WNP-2 FSAR Section 2.5.1.2.7).
These sediments consist of loose-to-medium
- dense, fine-to-coarse sand with scattered gravel.
Natural water content of the glaciofluvial sands is 2-4X.
Below approximate elevation 395 ft MSL, soils consist of very dense; sandy gravels with interbedded sandy and silty layers.
This zone, whicH is almost 200 ft thick, is known as the middle Ringold formation.
The groundwater table is located in this zone at approximately 380 ft MSL which is about 60 ft below ground surface.
Groundwater flow in the unconfined aquifer is toward the discharge boundary at the Columbia River approximately 3
1/2 miles east of the proposed disposal site.
The climate at tHe disposal site is characterized as mid-latitude semiar id.
The ar ea is subject to low humidities, large diurnal and annual ranges of temperatur es, and modest precipitation averaging 6 to 7 inches annually and occurring mostly as rain in the winter and spring months.
Natural recharge of the aquifer from precipitation is negligible since the evaporation potential averages 45 inches per year.
The predominant winds are from the northwest quadrant and average 7 1/2 miles per hour.
When winds are from the ENE or NE, as they are approximately 5X of the time, humidity at the proposed disposal location can exceed natural humidity due to the overhead cooling tower. vapor plume.
3.2 Waste Preparation and Burial The waste components described in Section 2.0 are stored onsite.
In preparation for burial the open outlets of the MSR tube bundles will be sealed with steel plates.
The tube bundles and the pipe spools will be wrapped with laminated vinyl fabric.
The miscellaneous MSR components will be placed in metal storage bins (spec.
US DOT Type A) and metal drums.
The disposal site will be prepared within the existing landfill excavation.
The contaminated components will be placed and backfill will be compacted in a
manner which minimizes voids and prevents subsidence.
Approximately three feet of soil will be placed over the contaminated components.
A land survey will be performed to record the burial site coordinates and posts and/or signs will be erected to mark the area.
0 I
The handling of the waste during preparation and disposal will be in accordance with Plant health physics procedures.
There may be external exposures to workers during this
- process, but the individual exposures should be no greater than would be associated with, disposal at a site licensed
- under, 10 CFR Part 61.
4.0 Evaluation of Radiolo ical and Environmental I act The radiological impact of the proposed waste disposal was evaluated by considering potential modes of exposur e including; 1) external exposure from standing on the ground above the disposal
- site,
- 2) internal exposure from the inhalation of resuspended radionuclides,
- 3) internal exposure from the ingestion of food grown on the disposal
- site, and
- 4) internal exposure from drinking potentially contaminated groundwater.
The most plausible post-burial radiation exposure is the external exposure accrued by persons working above the disposal site.
Calculations and assumptions used in the evaluation of this exposure are shown in Table 7.
The annual dose to an individual fr om external exposure is conservatively estimated to be 0.9 mrem.
The integrated lifetime dose to an individual is estimated to be less than 7
mr em.
Among the conservatisms is the assumption that the individual stands on the site 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> per year.
In fact, this ar ea is unoccupied except during infrequent landfilling operations.
Internal exposure from the inhalation of resuspended radionuclides and ingestion of crops grown on the disposal site is considered unlikely due to the proposed vinyl wrapping and the soil cover.
- Also, crop production is not a land use anticipated for the
- site, at least during the term of the Supply System's control of the property.
An internal exposure due to consumption of groundwater contaminated by waste materials is not considered plausible for several reasons.
First, with the low precipitation, there is no mechanism to remove the contamination from the components and transport it 40-50 feet down to the water table.
- Secondly, there are no wells drawing from the unconfined aquifer 'downgr adient of the disposal site.
There are two wells in use at the Supply System's WNP-I site about 7000 ft east of the proposed disposal location.
However, these wells are 372 ft and 465 ft deep and",
based on stratigraphy and water. quality data, appear to draw from a
semi-confined aquifer in the Ringold conglomerates and the upper fractured basalt flow.
Based on these
- factors, the groundwater pathway is not considered realistic.
Nevertheless, even if it were assumed that all the radioactivity reached the groundwater beneath the disposal site; the concentration of Co-60, the radionuclide with the longest half-life, would be reduced by a factor of 6000-7000 at the WNP-1 wells due to radioactive decay and sorption (WNP-2 FSAR Section 2.4.13.3).
There would be additional reduction due to dispersion in the aquifer,.
The nonradiological environmental impacts of the disposal will be negligible.
The proposal does not involve the disturbance of new ground nor.
does it represent a
new land use.
The area has been previously excavated for borrow
'aterial and backfilled with native soils and construction debris.
The material which has been landfilled in the area is dry, nonhazardous solid waste which will not create moist, acidic conditions conducive to movement of the radionuclides.
The waste components ar e scrap metal and are not a concern with respect to hazardous waste regulation (see 40 CFR 261.6(a)(3)(iv)).
I Ih
5.0 Sunmarg Contaminated tube bundles and pipe spools presently in storage at WNP-2 require disposal.
If, these components were packaged and disposed of as radioactive
- waste, the disposal would cost approximately
$305,000 and use approximately 7800 ft3 of licensed bur ial space at the US
- Ecology, Inc. site on the Hanford Reservation.
The Supply System proposes to dispose of these components by burial on the WNP-2 site at a cost savings of approximately
$270,000.
Neither the material to be disposed of nor the disposal operation will present an undue radiological risk to public health and safety.
In addition, the disposal will not adversely affect the environs.
Therefore, the Supply System is requesting approval of onsite disposal in accordance with 10 CFR 20.302(a).
Table 1.
MSR Tube Bundle Radiological Survey Data External tlSR Tube Exposure Rate Bundle No.
(mR/hr) 0.2-
Background
1.0 Near Head 8.0 Near Head
0.2 Background
0.2-0.3-
Background
0.2
Background
20-Near Head 20 Near Head External Smearable Contamination (dpm/100 cm')
1,000 1,000
<1,000
<1,000
<1;000 3,000
<1,000 1,000 Internal*
Exposure Rate (mR/hr) 0.1 3.0 6.0 0.2 0.2
<0.1 12,.0 8.0 Internal Smearable Contamination (dpm/100 cm')
<1,000 100,000 120;000 2,000
<1,000
<1,000 300,000 100,000 Taken in center of hemispherical head
8 1
Table 2.
MSR Tube Bundle Data and Radioactivity Content Calculations A.
MSR Tube Bundle Data 1.
Tube bundle heat transfer area 1st stage
= 2nd stage
= 22,600 ft'2.1E+7 cm')
2.
Tube bundle Weight 1st stage
= 27,200 lb (1.23E+7 gm) 2nd stage
= 33,200 lb (1.51E+7 gm) 3.
Tube bundle volume 390 fthm (1 1E+7 cms) 4.
Misc. assembly area 1000 ft'9.3E+5 cm')
5.
Misc. assembly weight 5000 lb (2.3E+6 gm) 6.
Misc assembly
- volume, 325 ft'9.2E+6 cm')
B.
Radioactivity Calculations 1.
Radionuclides
~(seto e
Half-life (yrs)
Av
. Distribution *(g)
Mn-54 Co-60 Zn-65 0.857 5.27 0.67 1.5 50 48.5
- Estimated by taking aver age of internal smears and germanium analysis of tube piece.
2.
Radionuclide Content a.
Hemispherical heads The radionuclide activity in the hemispherical heads was estimated from exposure rate measurements as follows.
x(R/hr)ts ~ds x MeV x Pen/> (cm'/gm) x 1.6E-6erg x 10'ad x 3600 sec x
4nr'mem
~erg gm br
i<here:
x = avg.
exposure rate measured in hemispherical head
= 3.7 mR/hr dps
= estimated activity per head NeV/d = 3.074 for Co-60 and Zn-65 per Rad Health Handbook Jfen/p
= 0.028 cm'/gm for 1-NeY photons per Rad Health Handbook r = 33 cm avg. radius of hemispherical head (head is divided in two by divider plate)
Solving for dps:
0 dps
=
x (R/hr) h.- 0 R sec hr d
= 3.7E-3R/hr 4.
- 0 R.sec hr.d
= 8.8E+6 dps 8.8E+6 dps x
uCi 3.
+
2.4E+2 uCi
~P~*
2.4E+3 uCi x 2 half hemis here " 8 tube bundle
= 3.8E+3 uCi
= 3.8 mCi b.
NSR tubes and miscellaneous components The germani'um results of a 30.4 cm'iece of NSR tube are as follows:
~Isoto e
'n-54 Co-60 Zn-65 Total Estimated Activity (uGi) 3.7E-5 1.4E-3 1.8E-3 The total activity in all the tubes is calculated as follows:
2.1E+7 cm'/tube bundle x 8 bundles x 3.2E-3 uCi
= 1.8E+4 uCi
= 18 mGi 30.
cm The total activity in the miscellaneous components is calculated as follows:
3.2E-3 uCi x 9.3E+5 cm' 98 uCi
3.
Radioactivity per unit mass 21.9E+3 uCi*
+6 gm +
4 tube bun e x
+
m
+
tu e bund e 2.0E-4 uCi/gm tu e un e x
+
gm)
Note:
There are four (4) 1st stage and four (4) 2nd stage tube bundles.
4.
Radioactivity per unit area 21.9E+3 uCi
+
cm
+
+
cm
= 1.3E-4 uCi/cm' tu e bun e) 5.
Radioactivity per unit volume 21.9E+3 uCi
= 2.3E-4 uCi/cms 9.99+
cms
+
+
cm~
x 8 tu e bund e)
- Includes activity from hemispherical
- heads, NSR Tubes and miscellaneous components.
Table 3.
Gama Ray Spectrometry Nuclide Suaeary of NSR Tube Bundle f8 SAMPLE OUI"!HER."
BAYiPLE VQLUNE=
SANPI E GATE SAVVYLE TIh!E 88-85~8 1.000001 12-DEC-88 1 ~ 00 LIVI'= "l IHE RFAL TIh F
.)EAD TTI'~iE 1800 1850 CEQ(RETRY: 47mm Pl ~inch~.(:
She~i 4 1 '"- QRTi ACQUISIT IQhl STARTED; 12-DEC."88 f'7". 0h: 00 hlUCLIDE TIl"IE GF CQUHT TIHE CGRRECTED PERCEh! T ACTIVITY ACTIVITY UNCERTAIl'!TY Uci /cc Uci/c..
CQUNTXi~lG 2 S
j'!n-54 Ca-60 Zn-*5 AP-51 1
- 4. 'P5. E-Oi;:.
i-747E-Oi
- 1. 482E-01
- 2. 587E-0='.
956E-0 i
- i. 747E -01 1 4$">E-0i
- 2. 589E-Oa
- 7. "
.8 7
TQTAL ACTIVITY=- 3. ~iE-01 Uci /cc
Table 4.
Pipe Spool Radiological Survey Data Pi e
S ool No.
Internal Exposure Rate (mR/hr) 0.4 0.25 0.4 0.6 Internal Smearable Contamination (d m/100 cm>)
<1000
<1000 3000 3000
Table 5.
Gamna Ray Spectrometry Nuclide Sugary of Pipe Spool
$1 SAMPLE NUMBER:
SAMPLE VGLUi"iE.--
SAMPI E DATE SAMPLE TIME BB-B47B
- 1. 888881 99-DEC-BB
<<5!88:88 LIVE TI MF REAL TIME DEAD TIME /:
1B88 iB89 8
GEOMETRY:47mm Filter Shel%
1 -- GRTZ ACGUISITIGM STARTED:
O'P-DEC-BB i5:48".88 blUCLIDE TIME F
CGUWT T'E CGRRECTFD PERCEiWT ACTIVITY ACTIVITY Ul4CERTAINTY Uci/cc Uc'/c<<CGUiWTIXB 2 S
Mn-54 Ca-68 Zn-65 Sb-125 K-48 AP-5i, 1
- 7. 681F-84 4.6B2E-84 3.127E-83
- 2. ib'iE-82 Z.291E-82 B.281E-84 7.681F-84 4.6B2E-84
- .6 1
~ 2 1.4 15.5 1
TGTAL ACTIVITY= 6.1BE-82 Uci/cc
Table 6.
Pipe Spool Data and Radioactivity Content Calculations 1.
Length (1):
6 ft (183 cm) 2.
Diameter (d):
3.1 ft (94.5 cm) 3.
Thickness:
1 in carbon steel 4.
Surface Area (8 x d
x 1):
/7 x 94.5 cm x 183 cm - 5.4E+4 cm2 5.
Mass:
2300 lb (1.04E+6 gm) 6.
Volume:
(~1 d2/4 x 1):
1Y x (94,5 cm)2/4 x 183 cm 1.28E+6 cm3 1.
Radionuclides Hn-.54 Co-60 Zn-65 Sb-125 0.857 5.27 0.67 2.76 Av Di i
i n
3.5 35 61 0.5 2.
Radionuclide Content The radionuclide activity (Ci) was estimated from exposure rate measurements taken in the center of the pipe as follows*:
I" C D
~ (2 tan 1/h) p r
where:
DP - avg.
exposure rate in center of pipe 0.41 mR/hr P
weighted avg. specific gamma ray constant for nuclide mix - 6.4 R
cm2 per hr mCi Cl estimated activity per unit pathlength in mCi/cm r
pipe radius 47.2 cm 1
- length of pipe from end to center - 91.4 cm h
distance from pipe to center of pipe 47.2 cm
Solving for Cj:
Dp '
p
-1 2
P (2tan 1/h) 6 4 ~~~
x 2tan 1 ~
m 'mCi 47.2 Total Activity:
1.6E-3 mCi/cm x 183 cm/pipe x 4 pipes 3.
Radioactivity per unit area 1.6E-3 mCi/cm 2
$.4F~~
5.6E-3 uCi/cm x 4 pipes 4.
Radioactivity per unit mass
~~
x 4 pipes pipe 2.9E-4 uCi/gm 5.
Radioactivity per unit volume 3
1.2JE~N x 4 pipe 2.3E-4 uci/cm 3
- Taken from page 295 of "Introduction to Health Physics",
Herman
- Cember, 2nd Edition.
Table 7.
Estimated Annual External Exposure to an Individual From Standing Above the MSR Tube Assemblies and Pipe Spools Average Average Surface External Concentration Depositiog Dose Factors
~l I
A.
HSR TUBE ASSEMBLIES Covered Annual Dose Rate Dose
~~egg//
gi~rm Hn-54 Co-60 Zn-65 B.
PIPE SPOOLS
- 3. 4E+0 1.2E+2 1.1E+2 3.4E+5 1.2E+7 1.1E+7 5.8E-9 1.7E-8 4E-9 2.0E-6 2.0E-4 4.4E-5 3.9E-3 4.1E-l 8.&E-2 Mn-54 Co-60 Zn-65 Sb-125
- 8. OE+0 8.1E+1 1.4E+2 1.0E+0 8.0E+5 8.1E+6 1.4E+7 1.0E+0 5.8E-9 1.7E-8 4E-9 4.6E-6 1.4E-4 5.6E-5 9.3E-3 2.&E-1 1.1E-l TOTAL 4.5E-4 8.9E-1 The average surface deposition was estimated by assuming that all of the radioactivity in the contaminated components was deposited on the top 10 cm surface and that the average concentrations of radionuclides in the wastes were the same as the measured concentrations.
External dose factors were taken from Table E-6 of Reg.
Guide 1.109, Rev.
1.
Table E-6 did not have an external dose factor for Sb-125, however its contribution to the annual dose is insignificant.
The covered dose rate was calculated using a dose attenuation factor of 1000 for a plane I
tl I
I 1
d b
Id-p f t f
I
.G..
d..
QJUUKllE i
i 1.
Figure 9.1-54.
Springer Verlag, Berlin, 196&.
Relevant data used was soil cover of 91.4 cm, mean soil density of 1.65 gm/cc and a photon energy of 1
MeV.
Annual dose was based on an occupancy of 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> per year.
60EI 98L I~ )I
~ I ) ~
IIII~
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Figure 1.
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Figure 2.
WNP-2 Site Photo
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