Environmental Defense Institute
Troy, Idaho
Comments
on
Revised Proposed Plan
Test Area North
at the
Idaho National Engineering
&
Environmental Laboratory
Submitted by
Chuck Broscious
On behalf of the Environmental Defense Institute
May 2003
I. Summary
The Department of Energy’s (DOE) Revised
Proposed Plan for Waste Area Group 1 - Test Area North (TAN) dated November
1998 [1] and the New
Proposed April 2003 remediation Plan [2] contain major
discrepancies with the Comprehensive Remedial Investigation / Feasibility
Investigation Report data and other internal INEEL waste characterization
report data on TAN. [3] (d) Federal Register, May 26, 1998, Part II,
Environmental Protection Agency, 40 CFR Parts 148 to 271, Land Disposal
Restrictions Phase IV Final Rule These data discrepancies are in the range
of many orders-of-magnitude.
Fundamentally, any treatment plan and applied
technology for remediation must be based on reliable waste stream data. Otherwise, DOE will face another fiasco that
occurred at the INEEL Pit-9 waste
treatment program that was eventually terminated because of (among other
reasons) inadequate waste characterization.
An issue stressed in the comments below, and apparently ignored by DOE
and the regulators, is that both the TAN V-Tank liquid and the sludge
(tank heels) and contaminated soil must
be include in the calculus of determining an appropriate remediation treatment
technology and the selection of waste disposal sites.
Additionally, the 2003 Plan
fails to address all the tanks and other “buried” TAN waste issues.
Only
four of the V-Tanks are addressed (30,400 gal.) when there are at least six
V-Tanks (additional 100,000 gal.) and other TAN waste discharge sites with
major radioactive and hazardous waste contaminates.
These crucial issues add to the public’s
skepticism about DOE’s veracity to tell the truth about its radioactive and
hazardous waste crisis, in addition to the regulators willingness to adequately
enforce the law that if appropriately applied, would appear to prohibit
disposal of this waste on the INEEL site as DOE plans.
Therefore, the Idaho Department of
Environmental Quality (IDEQ) and the Environmental Protection Agency (EPA) as
regulators (in keeping with the Settlement Agreement that included “alpha
emitting mixed low-level waste” be shipped to a geologic repository out of
Idaho), [4] must not
allow this remediation program to proceed until DOE provides credible
justification for the radically reduced waste stream characterization data, and
the regulators offer credible analysis that the waste treatment and disposal
will comply with all environmental regulations. Moreover, the public must then be fully appraised via a new
revised Plan, so that informed decisions can be made concerning the remediation
alternatives.
II. TAN V-Tank Contaminates
of Concern
This discussion is an amalgam of previous
(12/98) Environmental Defense Institute comments on TAN with current (4/03)
remediation plan Comments in addition to EDI comments on the INEEL CERCLA
Disposal Facility (ICDF) because of overlaps of Operational Units (OU), and
DOE’s intent to dump the TAN waste at the ICDF. Due to the long half-life of the radionuclides and the
no-half-life of hazardous chemicals of concern at TAN, there is no credible
reason that in the intervening four years there has been any reduction in the
waste due to “decay.” [5]
The 2003 TAN plan contains data is radically
(orders of magnitude) inconsistent with earlier DOE data. Neither DOE nor the regulators offer any
evidence justifying these crucial data discrepancies.
The
2003 Plan notes the maximum concentration for V-Tanks 1,2,3, and 9, are
compared to DOE’s 1998 data on the same tanks for a few select contaminates in
the Table A below.
Table A (see
footnote # 1)
Maximum Individual
Tank Contaminate |
EPA Standard # |
DOE Data 1998
Liquid |
DOE
Data 1998 Sludge |
DOE Data 2003 |
Antimony |
0.006 mg/kg |
- |
308 mg/kg |
11.5 mg/kg |
Arsenic |
0.01 mg/kg |
- |
12.4 mg/kg |
3.45 mg/kg |
Barium |
2.0 mg/kg |
2,320 mg/kg |
600 mg/kg |
299 mg/kg |
Cadmium |
0.005 mg/kg |
330 mg/kg |
71.7 mg/kg |
22.7 mg/kg |
Chromium |
0.1 mg/kg |
286 mg/kg |
3,770 mg/kg |
1,880 mg/kg |
Lead |
250 mg/kg |
81.7 mg/kg |
3,190 mg/kg |
454 mg/kg |
Cesium-137 |
200 pC/L |
12,500,000 pCi/L |
6,370,000
pCi/g 6,370
nCi/g |
4,480 nCi/g |
Strontium |
8 pCi/L |
250,000,000 pCi/L |
7,070,000
pCi/g 7,070
nCi/g |
5,180 nCi/g |
Total transuranics
V-Tanks 1,2,3,&9 including plutonium, americium, curium and neptunium |
15
pCi/L (for drinking water); * 100 nCi/g (for
TRU disposal) |
275,406 pCi/L |
42,716
pCi/g 42.831
nCi/g |
26.4 nCi/g |
Notes
for Above Table A * It has been a
long-standing criticism of the regulators to allow DOE in joint publications
to offer contaminate units different
than those in the regulations (MCL) and not to present side-by-side those
MCL’s with samples in DOE publication data tables. This data unit issue confuses the public and exacerbates
distrust. #
The above EPA Maximum Contaminate Level (MCL) Drinking Waste Standards are
offered here only to provide perspective on how hazardous the TAN wastes are.
See 40 CFR 141.61, 141.62, 141.66. |
Since DOE plans to dump V-Tank highly
contaminated soils into the tank to absorb the liquid portion of the tank
contents, this will add to the total tank contaminate levels. Addition of soil to dilute the concentration
of the waste is expressively prohibited in RCRA (40 CFR 268.3). The 2003 Plan
acknowledges transuranic waste in the V-Tanks at 26.4 nCi/g (page 6) which is 2
½ times higher than the greater than 10 nCi/g waste acceptance restriction for
the ICDF. [6]
Additionally, a credible argument can be made
that both the tank liquid and the sludge must be combined to determine
if the waste elevates to the category of transuranic waste. The regulatory definition of transuranic
radioactive waste is 100 nano curies per gram (nCi/g) of elements with an
atomic number greater than 92 (i.e. above uranium) that also have a half-life
greater than 20 years. [7] The above
table shows major discrepancies in the sampling data and also suggests that
this waste is at the very least “alpha low-level” or “transuranic waste” (assuming inclusion of both liquid and
sludge (tank heels) and therefore, cannot be disposed of at INEEL as DOE plans
at the ICDF. See discussion below on TAN waste disposal.
Federal Court Justice Edward Lodge issued a
ruling on March 31, 2003 that found in favor of the State of Idaho’s contention
that a 1995 Settlement Agreement/Consent Order stipulates the removal of all
buried transuranic waste from INEEL.
This ruling ends a long-standing legal battle between the State and the
Department of Energy over what waste was included in the Agreement. Judge Lodge’s ruling states:
“The
express language of the [Settlement] agreement, when taken as a whole, expressly
requires that all transuranic waste be removed from INEEL. The parties
specifically define transuranic waste without any limitation as to its location
within INEEL nor any limitation to amount.
Thus the Court is able to unequivocally state that in viewing the
document in the light most favorable to the United States, the plain language
of Paragraph B.1 [of the Settlement Agreement] clearly represents the parties
intent at the time the agreement was drafted that the United States remove all
transuranic waste located at INEEL.” [8]
Additionally, the 2003 TAN Plan fails to
address all the V tanks and other “buried” TAN waste issues. Only four of the V-Tanks are addressed in
the 2003 Plan when there are at least six V-Tanks with major radioactive and hazardous
waste contaminates. V-Tanks 1,2,3,9,13,and 14 volumes are 130,400 gallons.
[DOE/ID-10557, Vol. IV, page 9-14] See table B below.
Unfortunately, the TAN plan still fails to provide remedial solutions that meet Applicable or Relevant and Appropriate Requirements (ARAR). Transuranic (TRU) or Greater than Class C LLW (as defined by statute) can not be dumped at the INEEL CERCLA Disposal Facility (ICDF) under current waste acceptance criteria (WAC) restrictions or Nuclear Regulatory Commission regulations on radioactive waste dumps because they must go to a geologic repository. [9] The ICDF itself is questionably in compliance with current regulations. See section III below. The Plans offers no substantive information about discrepancy of the maximum contamination levels related to individual Operational Units (OU). Consequently, the general public is effectively denied essential information upon which to make their own determination of whether the preferred alternatives were appropriate.
The Plan claims to be “the comprehensive”
CERCLA investigation into TAN. This is
not a “comprehensive” Plan because the ANP Cask Storage Pad, the Area 10 HTRE
Reactor Vessel Burial Site, and the TAN Pool have been excluded.
An example of DOE/ID’s myopic approach is the Test Area North (TAN) Comprehensive Plan’s alternative of insitu vitrification (ISV) of the mixed hazardous/radioactive waste tanks. In 1996, the Oak Ridge National Laboratory (ORNL) tried the same insitu remediation approach despite public challenges to environmental law violations. The ORNL insitu project exploded putting workers and the public at extreme risk. The TAN tank waste characterization is similar to the buried waste in ORNL’s insitu project.
Actually, the lessons learned are as much site
related as they are complex wide related.
INEEL tried a ISV project a few years ago and it exploded as well, and
the containment tent got fried (burned up). Similar failed ISV projects can
also be found at DOE’s Hanford site. Tragically, the IDEQ and EPA, as
regulators fail to inform the public about these failed ISV projects, and a
member of the public may (based on inadequate information) conclude that ISV is
a viable remedial technology for INEEL.
Table B
TAN V-Tank Site |
Contaminate |
Concentration |
Reference |
V-1 Tank Liquid (TSF-09/18) |
STP Lists Liquid and Sludge |
MLLW |
STP @ 6-3 |
|
Cobalt-60 |
101,000 pCi/l |
(a) Table A-6-10 |
|
Cs-134 |
16,900 pCi/l |
(a) Table A-6-10 |
|
Cs-137 |
12,500,000 pCi/l |
(a) Table A-6-10 |
|
Europium-152 |
83,800 pCi/l |
(a) Table A-6-10 |
|
Europium-154 |
93,800 pCi/l |
(a) Table A-6-10 |
|
Plutonium-238 (liquid) (sediment) |
7,030 pCi/l 103 pCi/g |
(c) page 15-17 |
|
Plutonium-239 (liquid) (sediment) |
3,400 pCi/l 95.8 pCi/g |
(c) page 15-17 |
|
Americium-241(liquid) (sediment) |
9,230 pCi/l 230 pCi/g |
(c) page 15-17 |
|
Gross Beta |
16,100,000 pCi/l |
(c) 59 |
|
Gross Gamma |
24,300,000 pCi/l |
(c)59 |
|
Gross Alpha |
19,800 pCi/l |
(c) 59 |
|
Tritium |
11,800,000 pCi/l |
(a) Table A-6-10 |
|
Total Strontium |
1,840,000 pCi/l |
(a) Table A-6-10 |
|
Total Activity Liquid Sediment |
40,400,000 pCi/L 15,000,000 pCi/g |
(c) 59 |
|
Mercury Barium Cadmium Chromium Lead Silver |
0.842 mg/l 2,320 mg/kg 330 mg/kg 286 mg/kg 81.7 mg/kg 18
mg/kg |
Likely Exceeds UTS mercury @ 0.15 mg/l barium @ 7.6 mg/l Cadmium @ .19 Lead @ .37 Silver @ .30 (a) Table A-6-10 & 11 |
|
Tetrachloroethene Trichloroethene |
1,800 mg/kg 23
mg/kg |
Exceed LDR UTS (a) Table A-6-11 |
|
Vinyl Chloride 1,1 Dichloroethene Chloroform 1,2 dichloroethene Carbontetrachloride Benzene Chlorobenzene |
|
All Exceed LDR UTS (c) 8 through 12 |
|
|
|
|
Tank V-2 TSF-09/18 |
STP Lists Liquid and Sludge |
MLLW |
STP @ 6-3 |
|
Cobalt-60 |
10,500 pCi/l |
(a) A-6-10 |
|
Cesium-137 |
20,200,000 pCi/l |
(a) A-6-10 |
|
Strontium-90 |
1,450,000 pCi/l |
(a) A-6-10 |
|
Gross Beta |
23,400,000 pCi/l |
(a) A-6-10 |
|
Gross Gamma |
38,500,000 pCi/l |
(c)59 |
|
Plutonium-238 (liquid) (sediment) |
63.9 pCi/L 103.0 pCi/g |
(c) page 15-17 |
|
Americium-241(liquid) (Sediment) |
18.6 pCi/L 84.0 pCi/L |
(c) page 15-17 |
|
Gross Alpha |
84.9 pCi/l |
(c) 59 |
|
Total Activity Liquid Sediment |
1,090,000 pCi/L 13,000,000 pCi/g |
(c) 59 |
|
Trichloroethene Tetrachloroethene Cadmium Vinyl Chloride |
All four chemicals/metals Exceed TCLP |
(c) 8 through 12 |
|
1,2-Dichloroethane Carbon tetrachloride Benzene |
All three chemicals at the TCLP level |
(c) 8 through 12 |
|
18 Hazardous Chemicals |
Exceed Universal Treatment Standards |
(b) 10-44 40 CFR 268.48 |
V-3 Tank (TSF-09/18) |
STP lists |
MLLW |
STP @ 6-3 |
|
Plutonium-238 (liquid) (Sediment) |
33.5 pCi/L 384.0 pCi/g |
(c) page 15-17 |
|
Plutonium-239(sediment) |
31.1 pCi/g |
(c) page 15-17 |
|
Americium-241(liquid) (Sediment) |
30.0 pCi/L 206.0 pCi/g |
(c) page 15-17 |
|
Uranium-233/234 |
13,300 pCi/l |
(b) A-83 |
|
Strontium-90 |
12,300,000 pCi/l |
“ |
|
Cobalt-60 |
14,800 pCi/l |
“ |
|
Cesium-137 |
4,230,000 pCi/l |
“ |
|
Ruthenium-103 |
13,600 pCi/l |
“ |
|
Tritium |
6,090,000 pCi/l |
“ |
|
Nickel-63 |
205,000 pCi/l |
“ |
|
Gross Beta |
28,300,000 pCi/l |
(c) 59 |
|
Gross Gamma |
2,230,000 pCi/l |
(c) 59 |
|
Total Activity Liquid Sediment |
30,500,000 pCi/L 28,000,000 pCi/g |
(c) 59 |
|
Trichloroethene Tetrachloroethene Vinyl Chloride |
All three chemicals/metals Exceed TCLP |
(c) 8 through 12 |
|
1,2-Dichloroethane Carbon tetrachloride Benzene |
All three chemicals at the TCLP level |
(c) 8 through 12 |
|
18 Hazardous Chemicals |
Exceed LDR Universal Treatment Standards |
(b) 10-44 40 CFR 268.48 |
V-9 Tank (TSF-09/18) |
STP Lists Liquid and Sludge |
MLLW |
STP @ 6-3 |
|
Americium-241(liquid) (Sediment) |
40,200 pCi/l 5,700 pCi/g |
(b) A-91 (c) page 15-17 |
|
Plutonium-238(liquid) (Sediment) |
170,000 pCi/l 28,600 pCi/g |
(b) A-91 (c) page 15-17 |
|
Plutonium-239/240(Liq.) (Sediment) |
45,300 pCi/l 7,180 pCi/g |
(b) A-91 (c) page 15-17 |
|
Uranium-233 |
12,400 pCi/l |
(b) A-91 |
|
Uranium-234 |
211,000 pCi/l |
(b) A-91 |
|
Uranium-235 |
6,900 pCi/l |
(b) A-91 |
|
Uranium-236 |
3,260 pCi/l |
(b) A-91 |
|
Uranium-238 |
972 pCi/l |
(b) A-91 |
|
Cesium-137 |
6,370,000 pC/g |
(b) A-91 |
|
Tritium |
353,000,000 pCi/l |
(b) A-91 |
|
Total Strontium |
250,000,000 pCi/l |
(b) A-91 |
|
Cerium-244 |
5,210 pCi/l |
(b) A-91 |
|
Cobalt-60 |
1,160,000 pCi/l |
(b) A-91 |
|
Total Activity Liquid Sediment |
603,918,070 pCi/L 14,225,396 pCi/g |
(b) A-91 |
|
26 hazardous chemicals/metals |
Exceed UTS Treatment Standards |
(b) 10-44 40 CFR 268.48 |
PM-2A TSF-26 V-13 Tank |
50,000 gallon tank |
STP lists Liquids and Sludge as MLLW |
STP @ 6-3 |
|
Cobalt-60 |
45,900,000 pCi/l |
(c) 31 |
|
Europium-154 |
93,000,000 pCi/l |
(c) 31 |
|
Cesium-137 |
2,900,000,000 pCi/l |
(c) 31 |
|
Strontium-90 |
2,850,000,000 pCi/l |
(c) 31 |
|
Cesium-134 |
18,100,000 pCi/l |
(c) 31 |
|
Total Activity Curies |
41,380,000,000,000 pico curies 41.38 curies |
(c) 31 |
|
31 Hazardous Chemicals/metals |
Exceed UTS Treatment Standards |
(b) 10-28 to 31 40 CFR 268.48 |
PMA-2M TSF-26 V-14 Tank |
50,000 Gallon Tank |
TSP Lists Liquid and Sludge as MLLW |
STP @ 6-3 |
|
Cobalt-60 |
191,000,000 pCi/l |
(c) 31 |
|
Cesium-134 |
2,000,000 pCi/l |
(c) 31 |
|
Cesium-137 |
9,420,000,000 pCi/l |
(c) 31 |
|
Europium-154 |
17,200,000 pCi/l |
(c) 31 |
|
Strontium-90 |
9,260,000,000 pCi/l |
(c) 31 |
|
Total Activity Curies |
25,900,000,000 pico curies 25.96 curies |
(c) 31 |
|
33 hazardous chemicals/metals |
Exceed UTS Treatment Standards |
(b) 10-28 to 31 40 CFR 268.48 |
V- Tank soil |
STP lists as MLLW |
54,120 pCi/g |
RE-P-80-090 @6 |
Sources:
DOE 1998 Data refers to the following reports cited here and DOE’s 1998 Tan Remediation Plan ;
(a); Work Plan for Waste Area Group 1, Operable Unit 1-10, Comprehensive Remedial Investigation / Feasibility Study, Idaho National Engineering Laboratory, US Department of Energy Idaho Operations Office, DOE-ID-10527, March 1996. Vol I, RI/FS
(b); Comprehensive Remedial Investigation / Feasibility Study for the Test Area North Operable Unit 1-10, Idaho National Engineering Laboratory, US Department of Energy Idaho Operations Office, DOE-ID-10557, November 1997. (RI/FS)
(c); Field Sampling Plan for Operable Unit 1-10: Test Area North, D. L. Michael, Lockheed Idaho Technologies Company, Idaho National Engineering Laboratory, March 1996, INEL-95/0304, Vol.III RI/FS..
(d) Federal Register, May 26, 1998, Part II, Environmental Protection Agency, 40 CFR Parts 148 to 271, Land Disposal Restrictions Phase IV Final Rule
Acronyms:
LDR = Land Disposal Restrictions (40 CFR 148 through 271)
TCLP = Toxicity Characteristic Leachate Procedure (40 CFR 148 through 271)
UTS = Universal Treatment Standards (40 CFR 148 through 271)
PRG = Preliminary Remediation Goals (EPA cleanup goals based on risk values 12/18/96)
STP = INEEL Site Treatment Plan generated by statute requirement of the Federal Facility Compliance Act
For
more information see Environmental Defense Institute’s Comments on Proposed
Test Area North Cleanup Plan, December 1998, available on EDI’s Website,
publications link.
III. Issues Related to Disposal
of TAN Waste at ICDF
The Department of Energy (DOE) Idaho National
Engineering and Environmental Laboratory (INEEL) issued a Record of Decision in
October 1999 to, among other things, construct an on-site mixed hazardous and
radioactive waste dump.[10] This decision
was made within the Superfund (CERCLA) process with the concurrence of the
State of Idaho and the U.S.
Environmental Protection Agency (EPA). Initially, this was welcome news since the
Environmental Defense Institute has for years criticized DOE’s illegal waste
“disposal” practices in dumps that would not even meet municipal garbage
landfill regulations let alone radioactive and hazardous chemical waste. After detailed analysis of the Record of Decision,
it is clear that DOE plans to repeat the mistakes of the past by siting the new
dump (called the INEEL CERCLA Disposal Facility) (ICDF) not only in a flood
zone, but over top of Idaho’s sole source Snake River Aquifer which sustains
more than 200,000 families. In short,
the issue is not the construction of the new dump, but the issue is where
it is to be built on the INEEL site. EDI’s position is that there are credible
alternative sites on the INEEL that are not over the aquifer or in a flood
zone.
Additionally, DOE is violating other
environmental laws by claiming that the CERCLA process waves the requirements
of the National Environmental Policy Act (NEPA) among other laws. Attorneys conversant in the regulations say
CERCLA only waive the permitting and NEPA requirements in the direct removal
and remediation of a contaminated site.
CERCLA does not in this case waive the RCRA permitting or NEPA
requirements on a major $85 million ICDF dump project. Specifically, the equivalent requirements
under NEPA would require DOE to evaluate, in an Environmental Impact Statement,
the credible alternative siting locations for the ICDF. This was never done. Yes, DOE evaluated alternatives for on-site
versus off-site disposal.......but not alternative on-site locations. Once again, the legal requirements are
obfuscated not only by DOE but also by the State of Idaho and the Environmental
Protection Agency. Since this appears
to be a “done deal” between DOE and the regulators, it appears the public’s
only recourse is litigation. Once again
the public’s rights have been trampled.
A
review of the available US Geological Survey (USGS) reports related to
INEEL flooding scenarios and flood control infrastructures, it is clear that
DOE and the regulators ignored this information. Moreover, DOE ignored USGS recommendation that additional
analyses are conducted prior to any final sighting decisions are made for new
waste internment and disposition of existing buried waste. Specifically, USGS recommended a two-dimensional
model to expand the 1998 USGS one-dimension
model to include the upper 95%
confidence flow estimates of 11,600 cubic feet per second for the Big Lost
River 100-year flood, and include modeling for the upper range limit of the
500-year estimated flow rate in the Big Lost River flood plain on the
INEEL.
DOE is constructing the ICDF as a step toward
meeting regulatory requirements in the Resource Conservation Recovery Act
(RCRA) Subtitle-C hazardous waste disposal criteria. After 25 years of thumbing
its nose at RCRA, DOE finally is making a gesture toward compliance after five
decades of mismanagement of its waste streams that cause massive environmental
contamination. Estimated cleanup costs
of this INEEL debacle are in the range of $19 billion that will come out of our
pockets as taxpayers. DOES’ decision to
finally comply with RCRA is marred by the wrongheaded choice of location,
when other on-site locations would not pose the same risks to the aquifer that
is already severely contaminated from INEEL waste.
DOE is constructing the ICDF immediately south
of the Idaho Chemical Processing Plant (ICPP) also now called INTEC mainly for
economic reasons. It is close to the
ICPP where much of the waste will be generated and it is near/over existing
waste water percolation ponds which are on the Superfund cleanup list, and it
is over extensive soil contamination caused from ICPP stack releases. In other words, “kill three wasted birds
with one stone.”
The US Geological Survey released a 1998 report
that modeled the median 100-year
flow rates in the Big Lost River (that flows by the ICPP) down stream of the
INEEL Diversion Dam (6,220 cf/s). The
USGS report cross section number 22 at the ICPP puts the median flood elevation
at 4,912 feet.[11] Again, this
is only the mean flow rate (as opposed to the maximum rate of 11,600 cf/s) of
just a 100-year flood, and not including any additional cascading events
like the failure of Mackey Dam. The USGS flood map shows the northern half of
the ICPP under water. There are only
five-foot differences between the ICDF (south end of ICPP) elevation of 4,917
feet and the USGS predicted elevation of 4,912 feet through the middle of the
ICPP. The USGS study also employed current modeling techniques and plotted 37
separate cross sections on the INEEL site.
The ICPP as a whole is about as flat as a table top with only a couple
feet change in elevation north to south.[12] The crucial
point here is that even the slightest variation in a Big Lost River flood would
put the ICDF underwater assuming the dump was on the surface. Proportionally less variation in floods
would inundate the dump the deeper the ICDF is buried below the surrounding
terrain.
An earlier USGS study in 1996 also estimated
the flow range for the Big Lost River at the INEEL; “The upper and lower 95-percent confidence limits for the
estimated 100-year peak flow were 11,600 and 3,150 cubic feet per second
(cf/s), respectively.” [13]
Since 1950, INEEL has experienced significant
flooding events (localized and site-wide) in1962, 1965, 1969, 1982, and
1984. In an effort to mitigate the
flooding problem, DOE built a diversion dam on the Big Lost River that is
designed to shunt flood waters to the south and away from INEEL facilities. USGS’s 1998 report that modeled the mean
(midrange) 100-year flow rate of 7,260 cf/s upstream of the INEEL diversion
dam. USGS estimated that the Big Lost median flow rate downstream of the
diversion dam at 6,220 cf/s with a thousand cf/s going down the diversion
channel for a total median flow rate of 7,260 cf/s upstream of the INEEL
diversion dam. [14] “This peak
flow was routed down stream [of the Big Lost River] as if the INEEL diversion
dam did not exist. On the basis of a
structural analysis of the INEEL diversion dam (U.S. Army Corps of Engineers)
assumed the dam incapable of retaining high flows. The Corps indicated that the diversion dam could fail if flows
were to exceed 6,000 cubic feet per second.”[15]
This USGS study acknowledged that the northern
half of the ICPP would be flooded with four feet of moving water, even at this
midrange (mean) flow rate. If ICDF excavation goes two feet below
present surfaces, it will be below the elevation of the mean 100 year flood
zone. Plans are to excavate ICDF pits most of the entire 50 feet to bedrock.
Since the radioactive waste will be extremely
hazardous for tens of thousands of years and flooding will flush contaminates
down into the aquifer, a conservative risk assessment would model the upper
95-percent confidence limits for the estimated 100-year peak flow of 11,600 cf/s. USGS has proposed this additional research
to DOE, but the Department is not willing to provide the funding. A USGS
hydrologist notes, “The flow of 11,600
cfs represents the upper 95 percent confidence limit flow for the estimated
100-year peak flow (Kjelstrom and Berenbrock, 1996, p6). Future modeling needs
are to model the area with this flow.
We’ve expressed this to the INEEL and also have expressed that the WSPRO
model used has limitations and that an application of more stringent models
(two dimensional) is needed to refine and better delineate the extent of
possible flooding of the Big Lost River.” [16]
USGS estimates the mean 500-year Big Lost River
flood rates at 9,680 cf/s (34% greater flow rate than the mean 100 year flood).[17] This 500-year
flood would inundate the ICPP and surrounding area. These potential hazards are being ignored when making hazardous
mixed radioactive waste internment decisions in these vulnerable areas despite
the long-term consequences and the potential for additional aquifer
contamination.
Cascading events also are not considered. This
is known as a worst-case scenario where one event triggers another event. For instance a 500-Year flood plus failure of Mackay Dam (built in 1917)
resulting in estimated flows of 9,700 + 54,000 cubic feet per second
respectively would be an example of a cascading event. Failure of Mackey Dam is
non-speculative in view of the 1976 failure of the Teton Dam of similar
construction and the fact that Mackey Dam lies within 11 miles of a major
earthquake fault line that produced the 1983 Borah Peak 7.3 magnitude
quake. An internal 1986 DOE report
that analyzed the impact of Mackey Dam failure scenarios notes that, “Mackay
Dam was not built to conform to seismic or hydrologic design criteria,”
and ”the dam has experienced
significant under seepage since its construction.” [18] This EG&G
study acknowledged that the ICPP, Navel Reactors Facility, and the Test Area
North (LOFT) facilities would be flooded with at least four feet of water moving
at three feet per second.
USGS did not consider cascading events but
noted previous studies showing that failure of Mackay Dam alone would result in
6 feet of water at the INEEL Radioactive Waste Management Complex (RWMC) waste
burial grounds. Other studies recognized by USGS note that, “Rathburn (1989, 1991) estimated that the
depth of water at the RWMC, resulting from a paleo-flood [early] of 2 to 4
million cf/s in the Big Lost River in Box Canyon and overflow areas, was 50-60
feet.” “If Mackey Dam failed, Niccum
estimated that peak flow at the ICPP would be at 30,000 cfs.” [19] Comparing
these flow rates with the USGS estimate 100-year mean flow of 6,220 cfs that
would flood the north end of the ICPP with four feet of water, and a Mackey Dam
failure becomes a real disaster potential with respect to the existing
underground waste tanks and underground spent reactor fuel storage at the ICPP.
DOE is relying extensively on the Big Lost
River Diversion Dam (located at the western INEEL boundary) to shunt major
flood waters away from INEEL facilities.
The last comprehensive analysis of this diversion dike system (below the
diversion dam) was conducted by USGS in 1986 in a report titled Capacity of
the Diversion Channel below the Flood Control Dam on the Big Lost River at the
INEL. In this study USGS estimated
a mean flow rate of 9,300 cf/s, 7,200 of which went into the diversion channel
and “2,100 cf/s will pass through two low swells west of the main channel for a
combined maximum diversion capacity of 9,300 cf/s. A sustained flow at or above 9,300 cf/s could damage or destroy
the dike banks by erosion. Overflow
will first top the containment dike at cross section 1, located near the
downstream control structure on the diversion dam.” [20] This USGS
study did not analyze the construction of the diversion dikes but they would
likely fail as did the upstream diversion dam, built at the same time, that the
Army Corps of Engineers found structurally deficient. “On the basis of a structural analysis of the INEEL diversion dam
(U.S. Army Corps of Engineers, written comments, 1997), the dam was assumed
incapable of retaining high flows. The
Corps indicated that the diversion dam could fail if flows were to exceed 6,000
cf/s. Possible failure mechanisms are:
(1) erosion of the upstream face of the dam that results from high-flow
velocities and loss of slope protections (rip-rap), (2) overtopping of the
diversion dam by flows exceeding the capacity of the diversion channel and
culverts, (3) piping and breaching of the diversion dam because of seepage
around the culverts, and (4) instability of the dam and its foundation because
of seepage.”[21]
Failure of the diversion dam and/or the
diversion channel dikes would also directly impact the Radioactive Waste
Management Complex (RWMC) waste burial grounds. A 1976 USGS report notes,
“The burial ground is within 2 miles (3.2 km) of the Big Lost River and
the surface is approximately 40 feet (12 m) lower than the present river
channel. Sediments in the burial ground contain grains and pebbles of
limestone and quartzite, suggesting that in recent geologic past, flood waters
of the Big Lost River flowed through the burial ground basin. Two eroded notches or ‘wind-gaps’ in the
basalt ridge bordering the west of the burial ground also suggest past Big Lost
River floods.” “A large diversion
system on the Big Lost River was constructed by the AEC to control flood waters
by diverting water into ponding Areas
A, B, C, and D. The nearest of these,
Area B is less than a mile [south] from and about 30 feet (9m) higher in
elevation than the burial ground.” [22]
USGS Arco Hills SE and Big Southern
Butte quadrangle topographic maps clearly show the RWMC flooding
vulnerability as do other USGS reports that note, “If [diversion] dike 2 [at ponding Area B] fails, large flows
will drain directly toward the solid radioactive waste burial grounds.” [23] These
vulnerabilities must be taken into consideration when DOE attempts to leave the
buried transuranic waste at the RWMC and not exhume and relocate it to a safe
permanent repository.
Building dams around the INEEL CERCLA Disposal
Facility (ICDF) as was done at the RWMC is not an acceptable flood protection
answer because lateral water migration will go under the dams and local
precipitation will be held in exacerbating the leachate conditions. The liner of the ICDF will not be capable of
maintaining integrity with the increased hydraulic pressure during a flood
because liners are only capable of blocking what minimal surface water may leak
past the cap and infiltrate the waste.
There are good legitimate reasons why dumps (even municipal garbage
dumps) are not allowed by statute in flood zones or above sole source aquifers. Dams by definition are only functional if
there is regular maintenance which cannot be assumed once DOE ends
institutional control of INEEL in a hundred years. Dumping the waste on top of the ground and mounding the cover
over it will result in the cap eroding over the long-term which, again, is
unacceptable. Regulator’s contention that there is a degree of efficiency in
co-locating the ICDF with the ICPP percolation ponds that they must be
remediated along with the “windblown” soil contamination area around the
percolation ponds not only defies common sense but is also illegal.
DOE must designate another location for the
ICDF that is not near a flood plain and not over the aquifer. DOE’s own study has identified at least two
such sites (on the INEEL) where the Lemi Range meets the Snake River Plain. [24] DOE has not
seriously considered these alternative sites as would normally be required
under the National Environmental Policy Act (NEPA), stating that the sites were
eliminated from consideration due to increased seismic activity. There is no
documented evidence of this alternative site analysis. No empirical risk assessment was conducted
to compare the relative risk of a location over a sole source aquifer and in a
flood plain (ICPP) as opposed to a site with a slightly higher seismic risk not
over the aquifer or in a flood zone (Lemhi Range terminus). Other credible
options include purchasing land contiguous to the northern end of the
INEEL site near the terminus of the
Bitterroot Range that also would be off the aquifer and not in a flood zone and
have more soil cover over the bedrock.
Another misguided project outlined in DOE’s
October 1999 Record of Decision is the construction of new ICPP process waste
percolation ponds midway between ICPP and Central Facilities Area to the
south. For a detailed analysis of this
project see the Environmental Defense Institute’s Ground Water Contamination
at INEEL Report available at http://home.earthlink.net/~edinst/
Nuclear Regulatory Commission restrictions
prohibiting citing radioactive waste disposal dumps on 100 year flood plains
must be observed. [ NRC 10 CFR ss 61.50
The reason for these restrictions is because the flood water will leach the
contaminates out of the waste and flush the pollution more rapidly into the
aquifer. Since these wastes will remain
toxic for tens of thousands of years, they must be disposed of responsibly in a
safe permanent repository. These issues
must be kept in mind also with respect to the ICPP high-level waste tanks that
are some forty feet underground as well as the underground spent reactor fuel
storage and calcine storage bins at the ICPP.
Water acts as a moderator and if the underground spent fuel vaults are
flooded, it could cause a criticality.
All of these underground high-level waste sites are extremely
vulnerable. Former ICPP workers recall stacking sandbags six feet high around
the plant during a Spring flood about ten years ago. The added external hydrologic pressure on the high-level waste
tank concrete vaults could collapse the vaults and the tanks inside, and thus
release the contents. These risks must be considered when DOE decides to leave
the high-level waste tank sediments permanently in place as a cost cutting
measure.
The ICDF sighting, engineering design, and waste
acceptance criteria (WAC) must be developed with public involvement through a
free and open discussion. The legal
requirements of the process are spelled out in the National Environmental
Policy Act that requires Environmental Impact Statements and public hearings. Only un-containerized wastes that can be
compacted during placement should be allowed so as to minimize subsidence
caused by container decomposition. Biodegradable, VOC, collapsible, soluble,
TRU, or Greater than Class C Low-level, and Alpha-low-level waste must also be
excluded from the ICDF dump and sent off-site.
Prior to completing the ICDF Title II Design, workshops should be
convened for stakeholders to comment on the proposal in addition to the NEPA
requirements. Waste Acceptance
Criteria maximum contaminate concentration levels must be determined from waste
sampling prior to being mixed with any stabilizing materials. In other words, ”dilution is not the
solution to pollution”.
USGS reports identified factors favoring
downward waste migration. “In order for
waste isotopes to be carried downward by water, four basic requirements are
needed: 1.) availability of water, 2.) contact of the water with the waste, 3.)
solubility or suspendability of the waste in water, 4.) permeability in the
geologic media to allow water flow downward.” [25] This USGS
report describes in detail how all four conditions are met at INEEL including
the solubility factor where they note “Hagan and Miner (1970) leached five
different categories of solid waste from Rocky Flats [the main source of
plutonium in the RWMC] with ground water from the INEL and Rocky Flats and
measured the plutonium concentrations and pH of the leachate. They found the highest Pu-239 concentration
in leachates from the acidic-graphite wastes, 62,000 to 80,000 ug/l plutonium
or (3.8 x 10 9 to 4.9 x 10 9 pCi/L).” [Ibid]
The most reliable indicators of contaminate
migration are onsite sampling data. Cesium-137, plutonium-238,-239,-240 were
all found at the 240 foot interbeds under the RWMC. [IDO-22056@74] Forty-one % of the samples from the 240 foot
interbeds contained radionuclides. [Ibid.@87] Other literature
confirmation of plutonium at 240 feet includes: "Radionuclides
(including Pu-238.-239.-240, Am-241, Cs-137, Sr-90) have been detected in soils
and in sedimentary interbeds to a depth of 240 feet beneath the RWMC, (Hodge et
al, 1989)." "Positive values
for Pu-238,-239,-240 were detected in samples obtained from the 240 foot
interbed in bore hole DO2."[DOE/ID-10183@134-145][DOE/ID/12082(88)
@14-16]
Radionuclides are also confirmed in the aquifer under the RWMC. [EG&G-WTD-9438@25] USGS water sampling data at the 600 foot levels, expressed in pico
curies per liter (pCi/l) show:
For more
information on the contaminate migration from INEEL buried waste see EDI
website publication on “Snake River Aquifer at Risk”. http://perosonalpages.tds.net/~edinst
In summary of
Section III, ICDF site selection is illegal under statutes Nuclear Regulatory
Commission (NRC) rules that prohibit sighting of radioactive waste dumps in 100
year flood plains (10 CFR 61.50) which the agencies are obliged to conform to
if their commitment to Applicable or Relevant and Appropriate Requirement
(ARAR) is genuine
This particular
argument revolves around the fundamental definition of the 100-yr flood
zone. USGS conducted an extensive study
in 1998 that defined the upper and lower 95% confidence level on the flow rates
for a 100-year flood.
1.
The upper rate is estimated at 11,600 cfs and the lower rate is 3,150 cfs
2. USGS chose for
some unknown reason (perhaps pressure from DOE) to plot only the mean flow rate
(average between upper and lower) of 6,220 cfs
3. USGS assumptions
base on previous Army Corps of Engineers and other EG&G studies that the
Diversion Dam would fail with flows in excess of 6,000 cfs so the diversion dam
was mostly discounted.
4. USGS plotting of
the mean 100 year flow rate does not define the flood zone. It only shows where the likely areas that
will be affected during an average flood.
This mean plot should never be used for making major facility siting
decisions.
5. The appropriate definition of the 100-year
flood zone is to plot the upper bound 95% confidence level flow rate, which
USGS attempted to convince DOE to fund, but were refused funding.
6. No credible
empirical rationale can be presented to define the 100-year flood zone based on
the plotting of the mean flow rate as DOE and the regulators are doing.
7. Given that the
upper bound 95% confidence level flow rate is nearly twice what the mean flow
rate .......this is a significant spread.
The apparent top
of the ICDF berm is about 10 feet above the USGS plotted mean of the
100-year flood at INTEC. Absent a
through USGS study that plots the upper level flow rate and the resultant
flooding given the near level topography of the INTEC environs, there is a lot
of uncertainty about whether the berm is high enough.
Additional
uncertainty is the ability of the berm to survive the three feet per second
rush of the flood and the erosion that would be expected to occur.
The ten-foot
berm would also be expected to erode over time from natural wind and
precipitation which would eliminate that minimal flood barrier. Who is going to be around in 200 years to
maintain that berm? If the berm was breached, is the liner adequate
to maintain integrity with a hydraulic head of nearly 50 feet?
500-year flood
MEAN is estimated at 9,600 cfs.....Claims of 1,000 year durability of ICDF
mandates inclusion of the 500 year flood impact. Cascading event of Macky
Dam.....++ 54,000 cfs
Cost benefit analysis did not take into account long term impact on the potential further contamination of the sole source Snake River Aquifer and how it would affect health and safety not to mention agriculture.
[1] Proposed
Plan for Waste Area Group 1 - Test Area North INEEL, December 1998, DOE Idaho
Operations Office.
[2] New
Proposed Plan for the V-Tanks Contents (TSF-09 and TSF-18) at Test Area North,
Operable Unit 1-10, USDOE Idaho Operations Office, April 2003.
[3] DOE 1998 Data refers to the following reports cited here and DOE’s 1998 Tan Remediation Plan ;
(a); Work Plan for Waste Area Group 1, Operable Unit 1-10, Comprehensive Remedial Investigation / Feasibility Study, Idaho National Engineering Laboratory, US Department of Energy Idaho Operations Office, DOE-ID-10527, March 1996. Vol I, RI/FS
(b); Comprehensive Remedial Investigation / Feasibility Study for the Test Area North Operable Unit 1-10, Idaho National Engineering Laboratory, US Department of Energy Idaho Operations Office, DOE-ID-10557, November 1997. (RI/FS)
(c);
Field Sampling Plan for Operable Unit 1-10: Test Area North, D. L. Michael,
Lockheed Idaho Technologies Company, Idaho National Engineering Laboratory,
March 1996, INEL-95/0304, Vol.III RI/FS.
[4]Settlement
Agreement in United States v. Batt, No.CV-91-0065-S-EJL, page 6. Alpha emitting
Low-level waste includes waste containing transuranics, generating greater than
10 nano curie per gram (nCi/g).
[5] Most of the major volatile organic compounds
(VOC) are also dense non-aqueous phase liquid (DNAPL) which settle to the
bottom of the tank liquids so few would be expected to vaporize out the tank
vents over a short period of time.
[6] There are two categories of waste containing
transuranics; 1.) waste containing transuranic elements in
concentrations greater than 10 but less than 100 nCi/g is called alpha
low-level waste. Prior to 1984 DOE called this material transuranic waste, but
then unilaterally and arbitrarily changed it to alpha LLW; 2.)
currently, waste containing transuranics in concentrations greater than 100
nCi/g is classified transuranic (TRU) waste.
[7] Also see 10 CFR 61.55(a)(7) sum of the
fractions rule for mixtures of radionuclides, and (a)(8) Determination of
concentrations in wastes.
[8] Settlement Agreement in United States v. Batt,
No.CV-91-0065-S-EJL.
[9] 10 CFR 61.56
[10] Final
Record of Decision, Idaho Nuclear Technology and Engineering Center, Operable
Unite 3-13, Idaho National Engineering and Environmental Laboratory, October
1999
[11] Preliminary Water-Surface Elevations and
Boundary of the 100 Year Peak Flow in the Big Lost River at the Idaho National
Engineering and Environmental Laboratory, Idaho, US Geological Survey,
Water-Resources Investigations Report 98-4065, DOE/ID-22148
[12] Topographic Map of Block 21, National Reactor
Testing Station (now called INEEL) showing works and structures, U.S. Atomic
Energy Commission, Idaho Operations Office, shows three feet change in
elevation between the north and south end of the ICPP.
[13] Estimated
100-Year Peak Flows and Flow volumes in the Big Lost River and Birch Creek at
the Idaho National Engineering Laboratory, Idaho, U.S. Geological Survey,
Water-resources Investigations Report 96-4163, L.C. Kjelstrom and C.
Berenbrock, 1996, page 9.
[14] Preliminary Water-Surface Elevations and
Boundary of the 100 Year Peak Flow in the Big Lost River at the Idaho National
Engineering and Environmental Laboratory, Idaho, US Geological Survey,
Water-Resources Investigations Report 98-4065, DOE/ID-22148
[15] USGS
98-4065, page 8
[16] Charles E.
Berenbrock, U.S. Geological Survey Hydrologist, March 25, 1999 email to Chuck
Broscious
[17] Estimated 100 Year Peak Flows and Flow Volumes
in the Big Lost River and Birch Creek at the Idaho National Engineering Laboratory,
U.S. Geological Survey, Water Resources Investigations Report 96-4163, page
11 shows flow rates for 5-year,
10-year, 100-year, and 500-year floods
[18] Flood
Routing Analysis for a Failure of Mackey Dam, K. Koslow, D. Van Hafften,
prepared by EG&G Idaho for U.S. Department of Energy, June 1986,
EGG-EP-7184, page 15
[19] USGS 98-4065, page 6
[20] Capacity of
the Diversion Channel Below the Flood Control Dam on the Big Lost River at the
Idaho National Engineering Laboratory, US. Geological Survey Water Resources
Investigations Report 86-4204, C. M. Bennet, page 1 and 25
[21] USGS
98-4065, page 9
[22] Hydrology
of the Solid Waste Burial Ground, as Related to the Potential Migration of
Radionuclides, Idaho National Engineering Laboratory, U.S. Geological Survey,
Open File Report 76-471, J.Barraclough, August 1976, page 8
[23] Probability
of Exceeding Capacity of Flood-Control System at the National Reactor Testing
Station, Idaho, U.S. Geological Survey Water Resources Division, P.Carrigan,
JR., 1972, page 4
[24] Moriarty, T. P., Feasibility of Locating Dry
Storage of Spent Nuclear Fuel on Idaho National Engineering Laboratory Land at
a Site That Does Not Overlie the Snake River Aquifer, November 1995
[25] USGS 76-471
page 68-69