ML20033F457
| ML20033F457 | |
| Person / Time | |
|---|---|
| Issue date: | 04/05/1985 |
| From: | Cunningham R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Jicha J ENERGY, DEPT. OF |
| Shared Package | |
| ML20033D963 | List:
|
| References | |
| FOIA-90-29 NUDOCS 9003210130 | |
| Download: ML20033F457 (8) | |
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$ 6./$/Z AO $ E Mr. John J. Jicha, Jr.. Director APR 0J M5 t pf; 6 7d'V"fjf.
Gjl D&D and Pyproducts Division f//-ty.
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u Office cf Defense Waste g., fq.q,8.9 ff.c 3:2'y>j y
and Byproducts Panagement M j < p, e +* ~~) f M l y % 0. # g ' g.
j Department of Energy u
Washir.gton, D.C.
20545 s
Dear Mr. Jicha:
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The purpose of this letter is to document the understanding gnd agreements
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W between the Department of Energy (DOE) and the Nuclear Regulatory Co-mission b
(NRC) staff relative to the licensing of a comercial facility to act as fj a demonstration of the use of WESF capsules in a wet storage-dry irradiation 7.;
mode. This understanding and agreements are based upon your letter of g
July 25,198A to me, discussions between Bill Remini of your staff and Jim Ayer j:
of mine, and the lease agreerent to be entered into between the DOE y
and the. licensee.
q o As a part of the DOE testing program, capsules will be periodically
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d provided to DOE by the licensee for exaninatien. Capsule selection e
and testing will be no more frequent than one per year for the first d
ten years AM no less frequent than the first, third, sixth, aM M
ninth year after first use. Since the lease agreement is to be ff renecotiated after ten years, subsequent testing aM sampling pisnt v'
will be reviewed at that time. Capsule selection shall be rade 1
with the concurrence of DOE and shall include consideration of I
capsule temperature and use history.
1
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3 o Because corrosion rate is a function of temperature it is ir=portant p
that the themal history of the capsule selected for testing be j
known. Thus, the demonstration shall include temperature monitoring C
of the surface of a capsule at the most restrictive location in the 1
d source array. The most restrictive location is construed as the
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site of the capsule that is at the highest temperature.
As.a n i
y alternative the site of a capsule selected in advance for testing r.ay be chosen as the monitored location. The method of monitoring d
shall be approved by DOE and WPC.
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o During the lifetime of use in the irrar'iator the surface tenperature of the monitored capsule shall not exceed 3000C and the limit of
%j thermal cycles between air and water shall. not exceed 12,000.
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9003210130 900312 r
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OILDERT90-29 PDR i
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P APR 0 51985 Mr. John J. Jicha, Jr. 3 s
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o As a minimum, the tests and analyses carried out on selected UESF l
j capsules by DOE shall be equivalent to those described in PNL aB67, j
Year 1983," by G. H. Bryan, which include examination for corrosion of the inner capsule. The test results shall be made available in a letter report from DOE to the.NRC,
^
o.The lease agreement requires return of WESF capsules to DOE "in the sj event that the destructive analyses of any WESF capsule removed from the lessee's facility... indicates detrimental effects which would potentially jeopardize safe 'acility operation...." We agree that corrosive penetration of 25 percent of the inner capsule f.'
wall constitutes detrimental effect sufficient to warrant resarpling y
and examination or return of all WESF capsules to DOE's control.,
s; Pased on the ahnve understanding and acreements, we will continue with our s
licensing activities relative to demonstration of WESF capsule use in a d"
cormercial irradiator. Where appropriate the license for the demonstration E
irradiator will be conditioned to reflect the foregning agrements.
If you 3
bave any questions or do not concur with the above understanding, pleate J..
1et us know as scon as possible.
A sincerely, a
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Original egned by gichard E. Cunmngham W
f Richard E. Cunningham, Director g
Division of Fuel Cycle and i.'
Material Safety Office of Nuclear Material i
Safety and Safegua rds l=4'.
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NMSS R/F 4
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i SSINS NO.: 6835 r
IN 85-01 q
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION p
0FFICE OF INSPECTION AND ENFORCEMENT f
WASHINGTON, D.C.
20555 n
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January 10, 1985 l
IE INFORMATION NOTICE NO. 85-01:
CONTINUOUS SUPERVISION OF IRRADIATORS
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Addressees:
d.
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Q All licensees possessing irradiators that are not self-shielded and contain Q
more than 10,000 curies of radioactive material.
h
Purpose:
3 3
This information notice is provided to alert recipients of a potential safety 4
hazard and violation of NRC license requirements which can arise if licensees i
do not provide continuous supervision of large irradiator operations.
"Large" h
irradiators are those which contain more than 10,000 curies of radioactive s
material and which are not self-shielded. Although proper supervision and o'
security also is important for smaller irradiators, they are not the subject of h
this notice.
a
$i It is expected that 1.icensees will review this r.otice for applicability to f~
their facilities, if appropriate, to precluce a similar problem occurring at
(
their facilities. However, suggestions contained in this information rotice do not constitute NRC requirements; therefore, no specific action or written
].
response is required.
h{
Description of Circunstances:
Some large irradiators operate 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day.
Recently a case came to our
[
attention in which in irradiator was left operating overnight totally unattended, y
The irradiator license specifically required the physical presence of a fully A
trained supervisor whenever the irradiator was in use. This provision of the
]
license is consistent with NRC policy and good safety practice that large.irra-i diators should be conthuously attended by a fully trained supervisor except i
when the radioactive sources are secured in their safe storage position.
2 Compliance with that requirement assures that a qualified individual is 4
-immediately available to respond to emergencies or other problems. Note that 3
10 CFR 20.203(c)(6) requires that large irradiators must be equipped with entry p,
control devices and alarms to make an individual attempting to enter the 3
exposure area aware of the hazard and to alert at least one other individual who is familiar with the irradiator and prepared to render or sunsnon assistance, y'
The NRC is closely reviewing this matter during inspections and licensing actions. Most irradiator licenses explicitly state that a trained person must be physically present whenever the irradiator is being used. The NRC regional n
office will contact separately any irradiator licensee whose license may not be clear with respect to physical presence.
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IN 85e01 i
Ii,.
J;nuary 10, 1985 Page 2 of 2 6
k No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the Material
[.
LicensingBranch(301)427-4203) in NRC Headquarters or the materials licensing 6
section of your NRC regional office, vt -
(
m 1:
J. Nelson Grace, rector R
Division of Quality Assurance, Safeguards, g>
and Inspection Programs Office of Inspection and Enforcement y,
n h
Technical Contacts: J. Hickey, NMSS M
(301)427-4203 q
L J. Hetzger IE a-(301) 492-4947 11
Attachment:
i List of Recently Issued TE Information Notices.
h a
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4 Q
; e,.;.. a.. w.. - n .. ; c. n.u: v,.v ' q g av.a e... ~ -:.-. vw .. c ,w....... b i c Attachment IN 85-01 4 f January 10, 1985 4 LIST OF RECENTLY ISSUED IE INFORMATION NOTICES h Infonnation Date of d Not[ceNo. Sub.iect Issue Issued to F In 84-94 Reconcentration.0f R'adio-12/21/84 All NRC material's 0 -nuclides Involving Discharges licensees other than M Into Sanitary Sewage Systems licensees that use
- j Permitted Under 10 CFR 20.303 sealed sources only g
84-93 Potential For Loss Of Water 12/17/84 All power reactor j Fr'om The Refueling Cavity facilities holding 4 an OL or CP h
- j 84-92 Cracking of Flywheel on 12/17/84 All power reactor Il Cumins Fire Pump Diesel facilities holding
- g 84-91 Quality Control Problem 12/10/84 All power reactor.
Of Meteorological facilities holding
.n 84 90 Main Steam Line Break 12/7/84 All pressurized b Effect On Environmental wcter reactor and r 0} Qualification Of Eauipment gas cooled power facilitfes holding j. an OL or CP a: 7 Lt ' 89 Stress Corrosion Cracking 12/7/64 All boiling water j In Nor.sensititeo 316 reactor facilities Stainless Steel holding an OL or CP g 84-88 Standby Gas Trestwot 12/0/84 All boiling water System Problems reactor facilities }g holding an OL or CP j n S 84-87 Piping Thermal Deflection 12/3/84 All power reactor i; Induced By Stratified Flow facilities holding S_ an OL or CP 2 84-86 Isolation Between Signals 11/30/84 All power reactor l Of The Protection System facilities holding
Equipment OL = Operating License CP = Construction Permit ) i,'. i x I, ' (.,. - { ' ..,Ji'y ]{ ']_;' 1.'s,,3 y, j., g _ __ __ l g yws.rc.cw;,; = c..e.. ...m.m.... ..v - j,. - - 7,.. o.s. c.,...(..,,;,...;r.7;;; u.,.rycm;,,j a.,. ; 4 4 C. PNL-4250-6 i0* UC-70 i n".. 1, ) 8 t. .c (p - . I 9y ^,4, + i 'a
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l i,g p -.4: - :3 NUCLEAR WASTE MANAGEMENT i SEMIANNUAL PROGRESS REPORT APRIL 1984 THROUGH $EPTEMBER 1984 I l '. s. b >1 Q' Comptied by } p J. L. McElroy and J. A. Powel? d Nuclear Weste Technology Progcam 'jl .Jb ',4 1 December 1984 w g-t,. i Prepared for 2 the U.S. Department of Energy under Contract DE-AC06-76RLO 1830 9 li .ij c 4-Pacific Northwest Laboratory
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Richland, Washington 99352 h b O a e y + s .,1.'1,.j,.
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/Jv'y'. ', * *. *. 7.* y,3 : j s, g*, , e , *.r,. 5 ..c: 9 c.'.r.:a./.L..+ su w L :. O;,:. ^ = - .. - x ,e. ~n. : m :.2:... n.. w w c... r-g s 1 o 1 1.47 Results with 7M or gnater hydroxide at tempeentures 9 above 140'C. It appears that these limits Earlier reports in this series described will relax somewnst after the complete data 12-month tests conducted with double-shell set is analyzed. g d slurry an$ future PUREX wastes at tempera-As is illustrated in Figures 1.26 and g , tures of 40 'to 100*C as well as 4-month tests 1.27, the overall corrosion rates are de-3 at temperatures to 100*C. In the lower ten-enesing with time. It is probat.le that high y-perature range, corrosion rates were below rates (>1 mil /yr) will continue to be seen f .the 1 mil /yr (0.001 in./yr) essign allowance for high-caustic sixtures close to the design j for all of the double-shell slurry composi-temperature of the tanks ( 180'C). d
- tions and most future PUREX compositions.
The final analysis of the 40 to 180*C $) The exceptions were dilute hydroxide / nitrate double-shell-slurry / fission product data will 3 solutions. In these cases, severe corrosion, be completed in November 1984. A formal so-gnator than 2 at1/yr with localized attack, mary report will be issued. .s f occurred in the most dilute cases, 0.001M OH-j and 0.01M N0j. With slightly higher concen-1.6 CES!UM CHL08t!DE COMPATIB!t!TY fj trations, about 0.tM OH* and 0.1M N0j, SCC ( All-05-15 8068P.) 3 h occurret. No SCC occurred in the double-G.11. Fryan - Program Manager ( k ft M slurry enepot-it19ns. N I in the higher-tempenture tests,140 tne*- Es o6lacetue cf chh study.e ao avcinate Y she oewpasibility of Wtsy-produced Cact with g 180,C, the corrosten rates in future PUAEX g 3,gg,,,,,,; ,,p,,g,,,g,4,,j,, k compositions ste+ed, a the average, no she thmal conditione chas wot.tf be.encoun -
- j significer.t temperatuae cepancers a after offsrs twelves a defShp of W ar.gv,*ude, terst k a geologia repovisory. A **condary 1
12 months exposure. However, tie interpction esperity, sti origh of Pitthf fou w+ 09 8A8 ou88r surfood of some "*r odPeules. of temocrature and composition was statis-2 tically significant, indicating that the [ effect of temperature is different for some Suman [.i compositions. For example, high-caustic com- ) positions (5 to 9M OH-) have significantly A program was started in FY 1982 to evalu-ate the compatibility of WESF(a)-produced r. higher corrosion rates at 180*C than at 140'C, while the opposite is true for low-cesium chloride (CsC1) with Type 316L stain-h caustic compositions (0.1 to 0.2M OH*). 1Hs steel ($3) under W wont Wrsal con- 'l Other compositions (generally 0.2 to SM OH-) ditions that will be encountered in a geo-show little difference in corrosion rates logic repository. The principal objective of
- i between the two temperatures.
the program is compatibility-testing of six The high-temperature, double-shell-slurry standard WESF capsules at a maxima metal / M data showed significant effects of compos 1, CsC1 interface tempentum of. -4%'C. N 2 tion, temperature, and the temperature / capsules are placed vertically in insulated containers and allowed to self-heat to the composition interaction on corrosion rate. Tentatively, based on separate analyses of individual data sets, the corrosion rate (a) N Weste Encapsulation and $tonge Facility at the Hanford $lte. exceeds the design limit for compositions 4 0 I f ^*I , /1 # 3 D [ * ', T '[ ' '. [ j ? ), q, 4 * *. i 8 8 g m. . a L :M.r < ~ 2. 11 :. M Y."4' N.' ~..; i& : 3.D.v' lS.%W'3 ~W N N K rp twv d.;. w ci.
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E FIGURE 1.27 Corrosion Rate Distribution for Mixtures at 180*C i i w g me _ I, a , j h. a,. [#['M U 8i,,. a [I.* ,k;{# p d .,,,g_ ,8 {, 4 ,_ ',T* .s. .c .r % -, c. .c., u-= .?. c s. .a...r, ,,7 ~ ; w r. n w. m t ,,,,; ~. m wr.;,;.. (( f I 1, 1.49 test temperature, where they are saintained estimated to be 40 um (0.0016 in.), whereas for intervals from 2,200 to 32,000 hr. After the maxima attack in the 17,544-hr capsule 't thermal aging, the capsules are destructively was estimated to be 260 um (0.010 in.). j examined to detemine the extent of metal Althougn it is not unusual in compatf-j.i attack by the cesium chloride. The 17,544-hr bility-testing with radioactive materials to u capsule was examined in FY 1984 have wide vaMations in attact with replicate OuMng a pHor examination, it was found tests, the differences in the level of attack q!/ that one of the aged test capsules exhibited among the 8784-hr the 17.544-hr and the discoloration and pitting on the outer sur-4382-hr capsules appear to be greater than S face of the inner capsule. The damage was variations normally encountered. A plot of ih attributed to problems encountered in the the maximum metal attack observed in each ~ electropolishing operation, which is used to test capsule as a function of exposure time 4 q decontaminate the inner. capsule after it is (Figure 1.28) shows that the attack rate co-loaded with the CsC1 anet welded shut. A creases with time. As expected. Additional Q sthey was carH4d out in n 1994 to 1) deter-data pot :ts are needed, heuever, to determine j cine wther the pttting was usociated with with more certaint.v the form o? the corrosion 1 the electrepoltsning opera'sior., 7) identiS rata equation; the t'ata wilt Do generated } accontatis solution (s) *.o the pr%1em, and feco' tap 4ular, alrears u9 der test. 9 u
- 3) estatlish tne effect, if any, on the cap-it uhould be notad tr.ac the o*1gie:#1 oa' sis i
I sule's bnetene integHty. for solstit.g th6 450*C test tamnerature wes i Anether s)ertal study p6ctormed ta FY 1984 a projn ted,rea/thonnel loading limitation .r 1 was that of enmir.ing two espsules from the in a h petketical repository. 3 hE5F storage pool to establi'sh tW1 extent of y ' corrosion in storage. This renert sunenarizes WEsf Pittine Study 4 J. R. Divine program accompitshments in FY 1984 y Pits on the exterior surface of the inner x! Thermal Aging Tests - G. H. Bryan WESF capsule were observed on four 316L $$ ?q capsules. These appeared to be associated d Test capsule No. C-1486 was removed from with the contact points of the rack in the its insulated container after being held at WESF electropolishing unit used for decon-temperature for 17.544 hr. The time-averaged tamination of the capsules. maxima metal /CsC1 interface temperature for The operating parameters for the electro-the test period was 454*C. The capsule was polishing process at lESF were saamined for ./ shipped to ORIS for sectioning and metallo-their possible effect on capsule, pitting. 8 graphic examination. ORIIL completed the Within a reasonable range of, conditions a metallographic examination of that capsule as duMng nonnel operations, pitting is not ex-well as the 8784-hr test capsule (C-1451), pected. A chloride concentration of 100 ppe, I which had been shipped to ORit. in FY 1983. more than believed to be reasonably present Contrary to expectation, setal attack ob-in the electropolishing bath, roughened the } served in the 8784-hr capsule was much less surface only slightly. Variations in tem-than that observed in the capsule tested for perature, current density, and time, and in N 4392 he as well as the 17,544-hr capsule. concentrations of dissolved metal and phos. The maximum attack in the,8784-hr capsule was 'phoric acid over the expected ranges were 4 e 4 (* F 9 W y8 e 8 9 4 yf T,* j s. f ,y g e g 4 ~
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l 4 1 1 1.$0 3m, 6 mo. L ve, 300 u,2 1 4 9 J' ~ at0'C*1983.1984 5 h" 9 250 8 to m 4 ( [f l 200 8 { b .a OI '~ ! 150 6 4 vM 1s t N j t! o } ~ 100 4 i M. m, j 4 d ~ O I 50 - N 2 l I/ g ' { 0-d+. 0 4.000 % 007 u.000 i6.0C 0 j 1 1 -O e nn,eu.. no sj Jh F14tlRE 1.28. Maximus Metal Attack as a Functica of Exposure Time e,> l. f.; also shown to be unlikely causes of pitting. sufficient to ensure that the integrity of h The most likely cause of the observed pitting the WE3F capsules is not threatened during { D is believed to be the deterioration, with service because of the pitting. No consid* d i use, of the rack, which leads to a nonunifore eretion was taken of any corrosion of the h distribution of current. The presence of inner capsule surface by the cesium chloride. j f-point contacts between the capsule supports I f and the capsule leads to rapid localized dis-Examination of utSF pool Cell Capsules - solution of the capsule and the formation of G. H. Bryan j pits. l [d - The maximum pit' depth achieved under Two nESF cesium-chloride capsules were g worst-case laboratory conditions was about taken from the WESF storage pool and shipped ?; 30% of the. capsule well thickness. Never-to ORNL for sectioning and examination. Each, theless, though elimination of pitting is capsule contained >70 kCi of 137Cs at the [ desirable, metallurgical amasination and time of loading. One capsule had been in the mechanical testing 'of laboratory-pitted pool for 5 years and the other 8 years at the, ( specimens indicate that pitting is harmful time of renoval. Very little metal attack was !? only to the extent that it reduces the cross-observed in the stored capsules. Overal), di sectional area of the capsule. The strength attack observed in the storage c psules was h,l ' and ductility of the pitted specimens are about the same as that which occurs during t ig. s 1 4 ' G '* 1. Y ;.,.. , ' f f **.
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, [ $ \\ M.} '= o ' f' ' N * ?, 6' 'Q 't ~ 'A '^ -.....p.- ..,...o.. .. :. m m u..-. ~ -. w c.a w... m :.....:..n. s.,.. n w t. r..c _1 l C', p ) t 1 1.51 y ) the capsule loading operation. This indi-design of a system for distributing gnut in j catas that the capsules could be stored in a a large trench. A pump study was conducted ) water poc1 for long periods without suffering to aid in selecting a grout pump for Hanford's j j ) significant attack. grouting operation. A one-quarter-scale
- {
grout process was insta11e'd to test certain 1.7 HANFORD st0VT ttCHNOLOGY design features and to aid in establishing n { ( AR-0515-10 and AR-05-10 02 - g0760) operating specifications. 1 i R. L. Treat - Progra Manager o 3 f h' Regulatory Reavirements - 5. L. stain d The o6/soetse of shte progrow (a so ;ee-vide Apokuett #anfont Operosions wish each. Regulatory requirements that may be appli-M nioet suppere for d(epoetag gnused tow-Isuot g weases la shattop-t.md eises. cable to grouting at Hanford were reviewed R and will continue to be reviewed throughout $_uurnari_ the ;,rogram. Requirements reviewed include j snose centained in '.) DOC her 6820.3 for Regulatory requirements aps hedle to Montgament of Redf onctive Westes, 2) Wash-g grovt cisposal won reviuwed. Choical at.c inster. State Dar>gerous Weste Regulatiens j ] y radioactive 4ste species immortant to the (173 huac), 3) 4 riemorandum of Under. hj 1caggere perfsmente of dispesud grouts were StanditQ (14rJl t4*. wee's 00E anti EPA regarding j f'[ identified. A g1tt_ m prepared for disseri-' management 4ad disposal of r.onra21cecthe ^ y-asting infomat*ca 4 tM public on groutin7 hazardous w,stes, and 4) W MOU Detween 00E a mi et Hanford. Grout testing plans were pre-and epa regerding irplementation of the pared. The plans include the use of four Comprehensive Er:vironmental Response Compen- ) 'large lysimeter tear stations that are in-sation and Liability Aat (CERCLA) of 1980. d stalled during the reporting period. Arti-Interpretation of the re::uirements is YO ficially aged grouts will also be tested. continuing. 3 Pomeability measurements of a simulated 7 gj waste grout indicated that the grout is very. performance Assessment - S. L. Stein t impemeable. Analyses of potential water j [ percolation rates at the gnut disposal site Candidate weste streams for grouting were 2.' indicated that 100 to 1,000 years are re-examined in light of applicable regulations { quired for surface water to mach the water and potential grout perfomance require-(, table. The shortar travel time would require monts. This examination revealed that, in ] ), irrigation of the site or a change to a protecting tne ground water, the following wasta components are of primary importance 'i wetter climate. TC, 129, 14, and A plan for disposal of single-shell tanks radionuclides M 1, C h . by filling with grout was prepared. Chemical, actinides analyses of grovt formers and a radioactive chemical wastes: nitrates, chromates, j weste were performed. The analyses of grout xylene salts, and fluorides. f fomers highlighted the importance of careful A broader analysis of candidate waste streams ci analysis prior to use in grouting operations.. for grouting may result in identifying other d' Grout-flow tests were conducted to aid in the chemica) wastes that must be controlled. L d N u !. ) k '?i' ISM ' 'i.J O ' ' ' i' * 'L T ? C.' F . %_, '.,_..: +, x;. y ;0 L:y,q;;e-i .