ML18153C227
| ML18153C227 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 04/23/1990 |
| From: | Wick E NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Buckley B Office of Nuclear Reactor Regulation |
| References | |
| IEIN-89-027, IEIN-89-27, NUDOCS 9005290077 | |
| Download: ML18153C227 (19) | |
Text
CII 1_...J-v~U~.C:-
A UNITED STATES A
W!UCLEAR REGULATORY COMMISS~
WASHINGTON, D. C. 20555 NOTE TO:
Bart Buckley NRR/PD 2-2 FROM:
Everett Wick LLWM/LLTB A?;; ? ~, :Ji
-~PP t : *
SUBJECT:
VEPCO'S PLANNED USE OF JGC'S DRUM MIXER PROCESS FOR BITUMEN-SOLIDIFICATION OF LLW AT SURRY AND NORTH ANNA Per your request, a summary of our April 11, 1990 discussions with VEPCO representatives is enclosed.
We recommend that you refer VEPCO to an NRC information notice
[IN 89-27, LIMITATIONS ON THE USE OF *WASTE FORMS AND HIGH INTEGRITY CONTAINERS FOR THE DISPOSAL OF LOW-LEVEL RADIOACTIVE WASTE, March 8, 1989] which is germane to our discussions with them.
A copy of this IN is also enclosed.
~~~~zr~~
Everett Wick cc:
M. Tokar (w/encl.)
l~*----'-~=--==-=~:::::;;;:--~,.
r 9005290077 90042::::
I PDR ADOCK 05000280 I
1f PDC
MEETING
SUMMARY
DATE:
April 11, 1990 TIME:
10:00 -
11:00 a.m.
PLACE:
OWFN Room 14-B-13 PURPOSE:
TO DISCUSS VEPCO'S PLANNED BITUMEN-SOLIDIFICATION OF LLW AT THE SURRY AND NORTH ANNA SITES CHAIRMAN: Bart Buckley ATTENDEES:
Bart Buckley Charles Nichols Michael Tokar Everett Wick VEPCO NRR/PD 2-2 NRR/SPLB NMSS/LLWM/LLTB NMSS/LLWM/LLTB R. F. Saunders, Manager of Licensing D. A. Sommers, Supervisor-Licensing E. s. Grecheck, Assistant Station Manager-Surry
- w. D. Corbin, supervisor-Project Engineer G. L. Nash, Jr., Project Engineer T. Shaub
r,
- I
SUMMARY
- 1.
NRC's July 1983 approval of JGC's Topical Report (TR) for the Drum Mixer Process for Bitumen-Solidification of LLW was based on the acceptability of the process control plan.
The NRR review did not include consideration of the 10 CFR 61 requirements for structural stability of the waste form.
NMSS has not received or reviewed a TR for the waste form resulting from this process.
- 2.
We (NMSS) advised the VEPCO representatives that it is incumbent upon the licensee under 10 CFR 20.311 (Transfer for disposal and manifests) to certify that the characteristics of the waste form meet the requirements of 10 CFR Part 61.
We explained that the regulation does not require that the vendor submit a TR.
The Licensee can state the waste form meets the requirements of 10 CFR Part 61.
The NRC Inspector, however, may verify the basis for the Licensee's statement.
If the statement is not supported by acceptable test results, the waste cannot be shipped.
- 3.
VEPCO asked about the review cycle for TRs.
We explained that because of a backlog of approximately 12 TRs, the review cycle could be one to two years.
We also explained that performance by the vendor of the required tests of the waste form to demonstrate structural stability could require an additional 6-12 months.
- 4.
VEPCO invited cognizant NRC staff to visit the facility but no dates were firmed up.
e e
UNITED STATES NUCLEAR REGULATORY CO... ISSION OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS WASHINGTON, D.C.
20555 March 8, 1989 NRC INFORMATION NOTICE NO. 89-27:
LIMITATIONS ON THE USE OF WASTE FORNS AND HIGH INTEGRITY CONTAINERS FOR THE DISPOSAL OF LOW-LEVEL RADIOACTIVE WASTE Addressees:
All holders of operating licenses or construction permits for nuclear power reactors, fuel cycle licenses and certain by-product materials licenses.
Purpose:
This information notice is being provided to inform addressees of recent actions taken by the NRC concerning the stability of waste fonns {WFs) that contain Class Band/or Class C low-level waste. The actions pertain to completion by the NRC Office of Nuclear ~aterial Safety and Safeguards (NMSS) of reviews of vendor topical reports (TRs) on waste forms containing stabilized low level wastes or or, high integrity containers (HICs) for burial at low-level waste disposal sites.
It is. expected that addressees will review the actions listed in the attached status sunmary for applicability to their activities and consider actions, as appropriate, to avoid problems in disposing of certain waste streaffls.
Addressees are also expected to distribute the notice to responsible radiological staff and waste handling personnel.
However, suggestions contained in this information notice do not constitute any new NRC requirements; therefore. no specific action or written response is required.
Description of Circumstances:
This information notice applies to TRs that characterize solidified waste forms or high integrity containers that contain Class Band Class Clow-level waste from reactor WQSte streams, from fuel cycle facilities or from certain by-product materials waste streams. The,solidificatfon media for the waste forms typically have consisted of cement, cement/gypsum, polymer or bitumen.
The HIC materials are typically iron~chromiumcnicktl-alloys (i.e.i ferralium or austenitic stainless steels}, polyethylene-impregnated concrete, polyethylene, fiberglass/polyethylene or coated carbon steel (please refer to the status surnnary in Attachment 1).
NRC reviews of vendor topical reports on*solfdified low-level waste forms and on high integrity containers are issued as Technical Evaluation Reports (TERs).
A copy of each TER and the letter of transmittal to the vendor applicant is sent to the Agreement States in which the current LLW disposal sites are located.
IN 89-27 March 8, 1989 Page 2 of 6 Approvals of stab1lization media and HICs are limited to certain waste concen-trations or to certain wast~ streams which are stated in the TER and the letter of transmittal. Thus, not all waste concentrations er waste streams in the original TRs have been approved.
These restrictions or limitations could affect the ability of license~s to dispose of certain wastes.
An example of an approved stabilization medium (i.e., waste form) fs presented in Attachment 2.
The TER and the TR it covers are not legal requirements.
However, a user risks rejection of waste shipments by buridl site operators if waste forms or HICs are generated outside the limitations of topical reports approved by the NRC.
Waste generating licensees who desire to transfer low-level radioactive waste to a land disposal facility or tc a licensed collector and any licensed waste processor who treats or repackages wastes are reminded that they 1111st comply with the requirements of paragraphs (d) and (f), respectively, of 10 CFR 20.311.
URC regulation 10 CFR 20.311 requires the waste generator and/or processor, as pertinent, to certify, through the preparation of shipping manifests, that the transported materials are properly classified, described, packaged, and labeled and are in proper condition for transportation. For the purposes of this infor-mation notice, particular attention should be paid to paragraphs (d)(l) and (f){3),
respectively, of 10 CFR 20.311, where ft fs indicated that a licensee shall prepare all wast~s so that the waste fs classified according to 10 CFR 61.55 and meets waste characteristics requirements in 10 CFR 61.56.
One way for a waste generator or processor to ensure compliance with the Class Band Class C waste stGbilfty requirements of 10 CFR 61.56(b) is to process the waste 1n ac-cordance with the provisions and limitations of the NRC-approved topical reports on waste form stability *
. Discussion:
Background -
The Agreement States* have the licensing authority for the disposal sites with respect to whether specific HICs or WFs would be acceptable for disposal at their sites. An agreement, however, was reached in 1983 between NRC and the States that NRC woula provide* *central" review of TRs that would be applicable for all the disposal sites. Before the 1983 agreement the State of South Carolina ilad issued ten Certificates of C011pliance {Cs of d and had under review two additional requests for approval of HICs.
The State of Washington had two requests for approval. It was decided that South Carolina (Nevada and Washington had not yet issued any HIC approvals) would continue to accept the use of HICs that had alrea~ been issued a c of c.
For s~c~ HICs,.revocation of a C of C would take place only if a problem were ident1f1ea or 1f new information indicated that the HICs would not ineet the
- "Agreement Statt!" 111eans any state with which the NRC has entered into an effective agreement under subsection 274b of the Atomic Energy Act of 1954.
IN 89-27 March 8, 1989 Page 3 of 6 acceptance criteria. For new HICs that were described in TRs submitted to the NRC, the States would not issue Cs of C until th~ review had been completed by the NRC; it should be noted, however, that periodic tempcrary approvals or "variances" for l imHed quantities of certain types of HICs have been granted by the State of Washington.
For solidification processes, those processors who submitted informatior. to NRC in TRs submitted before June 30, 1984 would be acceptable under a grandfathering arrangement pending completion of the NRC review.
A list of HICs and solidification media that are currently accepted at Barnwell, Hanford 11 and Eeatty can be found in Attachments 3, 4, and 5, r*t:spec-tively. Solidificatior1 media and high integrity containers shown in Attach,nent 1 as "discontinued", "not approved* or "withdrawn* are not acceptable for disposal unless special provisions have been arranged with the disposal site{s).
A case where the NRC staff has concluded that a stabilization product is not capable of meetir.g 10 CFR Part 61 require,nents for waste form stability, unless special provisions are provided at the disposal site, involves the use of high density polyethylene (HOPE) high integrity containers.
As indicated in Attach-ment 1, such containers, as described in topical reports submitted by three vendors (Docket Nos. WM-18, WM-76, & WM-80), were not approved by the NRC.
In the list (Attachment 4) of stabilization media and containers approved by the State of South Carolina, however, it 1s shown that (beginning in 1981) several HOPE containers have been issued Certificates of co...,liance. Those containers continue to be accepted for disposal at the Barnwell site *on an interim basisn whilH South Carolina implemt:nts special provisions for disposal beginning April 1, 1989.
NRC-lic~nsed waste generators who wish to use polyethylene containers for the disposal of Class E and Class C wastes and who must co11ply with the provisions of 10 CFR 20.3ll(d) should either (1) place and ship the polyethylene container in ar. approved high integrity container (see Attachment 1 for a list of NRC-approved HICs} or (2) obtain assurance and documentation from the disposal site operatot that structural stability consistent with Part 61 requirements will be prcvided at the site. For example, stability requirements may be met b.) fllacing the waste in an approved concrete container or structure that provides stability after dfsp~sal. The State of South Carolina has author-ized the Barnwell Disposal Site Operator to receive class B & C waste fn HDPE/HICS for disposal in concrete overpacks~
Waste generators desiring to pursue any of these options shou1o,or.tact the facility optrator for procedural details.
Accepted Stabi 1 ization Procedures -
Licensees car. ensure that Clas's Band/or Class C low-level wastes will be accepted for burial at a disposal s_ite by doing one of the following:
- a.
solidifying the waste ir.to a form that is shown in the table.in as "approved 11 or "under revie\\o!" l:iy the NRC and which is accepted for disposal on ari interim or final basis by the sitl'd State;
IN 89-27 March 8, 1989 Page 4 of 6
- b.
placing the waste in a high integrity' container (HIC) that is shown ir, the tab le in Attachment l as "approved* by the NRC and for which a Certificate of Compliance or other State Apprcval doc~ment, as appropriate, has been issued;
- c.
solidifying the waste into a form (i.~.* using a Stabilization Medium) that has been approved by the States of Nevada, South Carolrna, or Wash irlgton for buria 1 at the Beatty, Barnwe 11, or Hanford sites, as appropriate (see Attachments 3, 4 and 5);
- d.
placing the wast~ in a HIC that has been approved by the State of Nevada or for which a Certificate of C0tr~liance has been issued by the States of South Carolina or Washington for burial at the Beatty, BarnWtill, and Hanford sites, as appropriate (see Attachments 3, 4 and 5).
The follo~ing paragraphs discuss specific issues related to the stability of waste forms and process control procedures.
Mar,y reactor licensees art! required to process Wa$teS only in accordance with the plant-spec1fic process control program (PCP). Generic (not plant-specific) process control procedures er programs are address~d in TRs that are also reviewed by NRC' s Office of t~uclear Reactor Regulation (NRR), except as noted in Attachment 6.
A sumn1ary of topical reports for radwaste volume reduction systems.that NRR has approved or has under review 1s presented in Attachment 6.
Variances in Processing Parameters -
Some mixtures cf wastes and solidification agents may react adversely with one another. These reactions may not be noticeable during th£ specimen tests per-to~d before the actual solidification occurs; therefore, it is important to be alert to variances in soHctfficatfcm par*ameters specified by PCPs, such as increasing temperature of the mixture and reduced amount of solidification agent required to fill the liner or other container.
An example of a situation where a licensee either operated outside the bour.ds of the technical e~aluatfon report (TfR) or mixed waste streams of questionable or unknown compatibility is described in Information Notice No. 88-08, 11Chemical Reactioris with Radioactive Wa!:>>te Solidification Agents*, March 14, 1988.
Cement-Solidified ~aste Problems -
The problem identified ir. Information Notice No. BS-08 is symptomatic of a number of mishaps that. have been observed in the field and in laboratory testing of
IN 89-27 March 8, 1989 Page 5 of 6 cement-solfd1f1ed low-level waste.
Such mishaps include but are not limited to waste fonns that failed to solidify completely and that swelled and/or disintegrated over relatively short times after solidification. Waste streams that have caused the most concern involve bead resin, decontamination solutions, borates, sulfates, and oils.
As illustrated in the example discussed in Infor-mation Notice No. 88-08, small amounts of secondary ingredients that were not anticipated to be a problem, and which may not have been known to be present 1n the waste at the time of processing, were later identified to be the cause of the difficulties encountered. This is a major reason why waste generators and processors should endeavor to store; handle, and process Class Band C low-level radioactive wastes within the boundary condft1ons,**estab11shed in the qualification test programs, that-are addressed in the vendor topical reports.
It will be noted (see Attachment 1) that NMSS has not yet approved any topical reports dealing with 10 CFR Part 61 stability qualification testing of cement-solidified Class B or Class C wastes.
This is a result of the complexity of the issues involving cement-solidfffed wastes.
The NMSS staff plans to host in 1989 a Workshop on Cement-Stabilization of Low-Level Waste.
Cement stabi-lization medium vendors, waste generators, laboratory researchers and industry consultants are expected to participate in the workshop, which is intended to provide an improved understanding of the technical concerns and which would lead to both short-term and long-tenn regulatory resolution. Interested persons and potential participants may contact Dr. Michael Tokar at (301) 492-0590 for further information. Suggestions regarding the workshop agenda and fonnat are welcome.
Status of Reviews -
As may be seen from Attachment 1, the status of topical report reviews is subject to change as reviews are completed and as new TRs or revisions to existing TRs are submitted for review. Thus, the lists of so11d1f1cation media or HICs that have been reviewed and approved by NRC and those that are acceptable at Agreement State sites may change.
Waste generators should remain *aware of the status.of TRs reviewed by NRC so as to be informed of any limitations or change in 11mitat1ons on use of solidffted media and HICs.
To assist the waste generators and others in this regard, updates of the status*.of NRC TR reviews w111 be issued at least annually.
Licensees may obtain copies of non-proprietary versions of the TERs and non-proprietary versions of the applicable TRs from NRC Headquarters or from the appropriate NRC regional office.
HI 69-27 March 8, 1989 Page 6 of 6 No specific action or written response is required by this inforn~tion notice.
A sunmary of topical report reviews is presented in Attachment l. If you have any questions regarding this infonnatfon notice, ~1ease contact the technical contacts listed below or the Regional Administrator of the appropriate regional office. A list ot recent information notices is shown in Attachmer,t 7 for background information.
tJ~~Lf~
~o~n T. Greeves, Acting Director Division of Low-Level Waste Management and Decoarnissfoning, NMSS Technical Contacts: Michael Tokar, NMSS (301) 492-0590 Attachments:
Charles Nichols, NRR (301) 492-0854
- 1.
Topica1 Report Review Status Su11111ary, Solidified Waste Form and High Integrity Containers (HICs)
- 2.
Example of Approved Stabilization Mediuar and Lin,1tations on Approved Waste Streams
- 3.
List of HICs and Stabilization Media Currently Accepted at Beatty
- 4.
List of HICs and Stabilization ft;f:dfa Currently Accepted at Barnwell
- 5.
List of HICs and Stabilization Media Currently Accepted at Hanford
- 6.
Topic~l Report Review Status Sunmary for Radwaste Volume Reduction Systems
- 7.
List of Recently Issued NRC Information Notices
TOPICAL REPORT REVIEW STATUS
SUMMARY
Attactrnent 1 IN 89-27 March 8, 1989 Page 1 of 1 SOLIDIFIED WASTE FORM AND HIGH INTEGRITY coNTAtNERS (HICs}
JANUARY 5, 1989 Office of Nuclear Material Safety and Safeguards Vendor Waste Chem General Electric DOW Chichibu Nuclear Packaging Nuclear Packaging LN Technologies Chem-Nuclear Hittman TFC Nuclear U.S. Gypsum ATI (U.S.Ecology)
VI KEM Stock.
Nuclear Packaging Chem-Nuclear Chem-Nuclear Hi ttrnan Nuclear Packaging LN Technologies Chem-Nuclear Chem-Nuclear Chem-Nuclear Chem-Nuclear LN Technologies LN Technologies Hittman ATI (U.S. Ecology)
Bondico Babcock & Wilcox Docket No.
WM-90**
WM-88 WM-82**
WM-81 WM-45 WM-85**
WM-93**
WM-18**
WM-80**
WM-76**
WM-51**
WM-91**
WM-13 WM-92**
WM-71 WM-19.**
WM-96**
WM-79**
WM-87**
WM-57 WM-47 WM-101 WM-97 WM-98 WM-20 WM-99 w.4-46 WM-100~
WM-94 WM-95 ill!
So.lidification (bitumen)
Solidification {polymer)
Solidification {polymer}
HIC (poly impreg/concrete)
HIC (ferralf1.111/FL-50)
HIC {ferralium/family)
HIC (stainless/poly)
HIC (polyethylene)
HIC (polyethylene)
HIC (polyethylene)
Solidification (gypsum)*
Solfdiffcation (bitumen)
Solidification/oil {cement)
Solidification {cement)
Solid/Encap {cement/gypsum)
Sol1dif1cation {cement)
Solidification {cement)
Solidification {SG-95)
HIC {316-stainless/SDS)
HIC (polyethylene)
, HIC (fiberglass/poly)
Solidification {cement #1)
Solidification {cement #2)
Solidification {cement #3)
Solidification (cement)
Solidification (cement/decon)
So11dificition (cement)
Solidification (bitumen)
HIC (fiberglass/poly)
Disposition Approved.
Approved *.
Approved.
Approved.
Approved.
Approved.
Approved.
Not Approved.
,Not Approved.
Not Approved.
Not Approved.
Discontinued.
Discontinued.
Discontinued.
Withdrawn.
Withdrawn.
Withdrawn.
Withdrawn.
Withdrawn.
Withdrawn.
Withdrawn.
Under review.
Under review.
Under review.
Under review.
Under review.
Under review.
Under review.
Under review.
Under review.
Had been approved for single waste stream for one year ending March 3, 1989.
Actions completed in Calendar Year 1988.
IN 89-27 March 8, 1989 Page 1 of 1 EXAMPLE OF APPROVED STABILIZATION MEDIUM AND LIMITATIONS ON APPROVED WASTE STREA,,!S VENDOR TYPE
\\~aste Chem Corpcrat1on Solidification Media (ASTM-D-312 Type III ox1d1zed bitumen)
DOCKET WM-90 WASTE STREAM{s)
Bead Resin Approved For:
Precoat Filter Cake with Powdered Resin Precoat Filter Cake with D1atomaceous Earth Evaporator Concentrates - Neutralization Waste Evaporator Concentrates - Floor Drain Evaporator Concentrates Decontamination Waste Mixed Resin and Filter Cake Waste CONCENTRATION LIMITATION ( s)
Waste Fonns must be prepared 1n Accordance with Process Control Program {PCP)
Waste Fann in 55-Gallon Drum or approved HIC Maximum waste loadings are as stated in Section A-3.3 of the WasteChem Topical Report, VRS-002, dated August 1987 or fn Table I of Appendix A of the NRC TER dated January 22, 1988 *.
IN 89-27 March 8, 1989 Page 1 of 1 LIST OF H!Cs AND STABILIZATION MEDIA CURRENTLY ACCEPTED AT BEATTY HICs Rariufacturer Pacific Nuclear Nuclear Packaging Ch1ch1bu Cement.
Chichibu Cement Stabilization Media
- 1. Aztech (General Electric)
- 2.
Bitumen* {Waste Chem and ATI)
- 3.
Chem-Nuclear Cement
- 4. Concrete**
- 5.
Dow Media (Vinyl Ester Styrene)
- 6.
Envirostone (U.S. Gypsum Cement)
- 7. Westinghouse-LN Technologies Cement
- 8. Stock Equipment Cement
- 9.
Hittman Grout Package Identification Number DSHS-HIC-TMI-01 DSHS-HIC-EA-50 0SHS-HIC-SFPIC200L DSHS-HIC-StPIC400L
- 10. Other solidification media and processes which have been approved by U. S. Nuclear Regulatory Comnission and/or the State as meeting waste fonn stability criteria.
Note: Oxidized Bitumen Only Note:
Concrete when*used as an encapsulation medium around a small volume of radioactive material, e.g., a sealed source centered 1n a fifty-five gallon drum containing concrete, shall have.a fonnulated compressive strength equa 1 to or greater than 2500 psi..
LIST OF HICs AND STABILIZATION MEDIA CURRENTLY ACCEPTED AT BARNWELL HIC Certificates of Compliance Issued to Adwin Equipment Company Chem-Nuclear Chem-Nuclear Chem-Nuclear Philadelphia Electric Comp.
Hittman Hittman Hittman Hittman LN Technologies TFC NUPAC NUPAC Ch1chibu Vermont Yankee Approved Stabi 11zat.ion Media*
Vinyl Ester Styrene Cement
PECO-HIC-1 Radlolc-55 HIC Radlok-100 HIC Radlok-200 HIC Radlok-500 HIC Barrier-55 HIC NUHIC-120 HIC HOPE 142 HIC FL-50 HIC Concrete HICs {x2)
HOPE HIC IN 89-27 March a. 1989 Page 1 of 1 Issued when 05/29/84 05/28/81 02/23/82 04/08/83 09/28/81 06/17/82 06/17 /82 05/05/83 09/31/85 09/01/83 11/01/83 08/20/84 09/26/85 08/12/86 10/10/83 Processes shall meet and have been evaluated fn accordance with the NRC "Technical Position on Waste Form* or other evaluation criteria specif-ically approved by the NRC.
Other stabilization media shall be accept-able for which a topical Report has been prepared and approval received from the NRC and the State.
Administrative controls at the Barnwell Site ~re necessary for the disposal of this waste fonn.
LIST OF HICs AND STABILIZATION MEDIA CURRENTLY ACCEPTED AT HANFORD IN 89-27 March 8, 1989 Page 1 of 2 HIC Certificates Of Corrplfance (C of C)
Package Identification C of C Number Manufacturer Number WN-HIC-01 Paci ff c *Nuclear DSHS-HIC-TMI-01 WN-HIC-02 Nuclear Packaging DSHS-HIC-EA-50 WN-HIC-03 Chfchibu Cement DSHS-HIC-SFPIC 200L WN-lUC-04 Chi ch 1 bu Cement DSHS-HIC-SFPIC 400L WN-HIC-05 Nuclear Packaging DSHS-HIC-EA 142A WN-HIC-06 Nuclear Packaging DSHS-HIC-EA SOA WN-HIC-07 Nuclear Packaging DSHS-HIC-EA 140A WN-HIC-08 Nuclear Packaging DSHS-HIC-EA 190A WN-HIC-09 Nuclear Packaging DSHS-HIC-EA 210A WN-HIC-10 Nuclear Packaging DSHS-HIC-EA SOC WN-HIC-11 Nuclear Packaging*
DSHS-HIC-EA 140C WN-HIC-12 Nuclear Packaging DSHS-HIC-EA 142C WN-HIC-13 Nuclear Packaging DSHS-HIC-EA 190C WN-HIC-14 Nuclear Packaging DSHS-HIC-EA 210C Other High Integrity Containers which have been approved by the State
LIST OF HICs AND STABILIZATION MEDIA CURRENTLY ACCEPTED AT HANFORD (CONTINUED)
Approved Stab111zat1on Media*
Aztech {General Electric)
Bitumen*"' (ATI and Waste Chem)
Chem-Nuclear Cement Dow Media (Vinyl Ester Styrene)
Env1rostone (U.S. Gypsum Cement)
West1nghouse-LN Technologies Cement Stock Equipment Cement Hittman Cement Concrete**'*
IN 89-27 March 8, 1989 Page 2 of 2 Only those stabi11zat1on media which have been evaluated or are 1n the process of being evaluated and are used with the stability guidance requirements of the NRC "Technical Position on Waste Fann" or are specifically approved by the State are considered acceptable stab111zatfon media. Other stabilization media and processes may be approved which have been reviewed and approved by the NRC and/or the State as meeting waste fonn stability criteria.
Oxidized Bitumen only.
- Concrete, when used as an encapsulation medium around a small volume of radioactive material, e.g., a sealed source centered 1n a fifty-five gallon drum containing concrete, shall have a formulated compressive strength equal to or greater than 2500 psi.
Attacflnent 6 IN 89-27.
March 8, 1989 Page 1 of 3 TOPICAL REPORT REVIEW STATUS
SUMMARY
FOR RADWASTE VOLUME REDUCTION SYSTEMS Office of Nuclear Reactor Regulation, January 1989 Vendor
- Aerojet Energy Conversion Co.
Hittman Nuclear &
Development Corp.
Report No.
AECC-1 HN-Rl 109-A, Revision 4 Title Fluid Bed Dryer Radwaste Solidification System (Cement}
Acceptance Date December, 1975 April, 1978 Werner & Pfleiderer WPC-VRS-001, Radwaste Volume Reduction April, 1978 Corporation Revfsfon 1
& Solidification System Dow Chemical Company DNS-RSS-001 The Dow System for Solid-June, 1980 ATCOR Engineered ATC-132A Systems. Inc.
- Newport News EI/NNI-77-7 Industrial Corp.
Chem-Nuclear CNSI-2 Systems, Inc.
{ 4313-01354-01)
- JGC Corporation JGC-TR-001
- Aerojet Energy AECC-4 Conversion Company
- Aerojet Energy AECC-2' Convers;on Company Associated Technologies AT:t,..VR-001 Incorporated NUS Process Services PS-53-0378 Corporation ification of Low-Level Radioactfve Waste from Nuclear Power Plants Radwaste Solidification September, 1981 System RWR-1 Radwaste Volume October, 1982 Reduction System Mobile Cement So11d1f1-March, 1983 cation System The Drum Mixer Process July, 1983 for Volume Reduction
& Solidification Mobile Volume Reduction October, 1984 System Radioactive Waste Volume November, 1984 Reduction System ATI Volume Reduction and Bitumen Solidification System Radwaste Solidification System Apri 1, 1985 May, 1985
e IN 89-27
~arch 8, 1989 Page 2 of 3 TOPICAL REPORT REVIEW STATUS
SUMMARY
FOR RADWASTE VOLUME REDUCTION SYSTEMS (CONTINUED)
Office of Nuclear Reactor Regulations, January 1989 Vendor Report No.
Chem-Nuc 1 ear CNSI-DW-11118-01 Systems, Inc.
ATCOR Engineered ATC-8019-1 Systems, Inc.
Nuclear Packaging,
- TP-02 Inc.
General Electric NEDE-30878 AZTECH Plant
- Koch Process KPS-1 Systems, Inc.
Associated Tech.,
ATI-VR-001 Incorporated Supplement l UNC Nuclear UNC-S 8000 Industries
- Aerojet Energy AECC-3 Conversion Company Westinghouse Hittman Nuclear, Incorporated Bartlett Nuclear, Incorporated Stock Equipment Company STD-R-05-011 BN-1 SRS-003 Acceptance Title Date CNSI Dewatering Control June, 1985 Process Containers ATCOR AVRS-80 Volume July, 1985 Reduction Process Nuclear Packaging, Inc. September, 1985 Dewater1ng System Transportable Modular December, 1985 YR-System 350 Low-Level March, 1986 Radwaste Volume Reduction System ATI Transportable Vol.
April, 1986 Reduction & Bitumen S0lid-ificatior1 System (TVR-111)
UNC Portland Cem./Soclfum August, 1986 Silicate Radwaste Solid-ification Systems Radioactive Waste Volume August, 1986 Reduction System Hittman Mobile October, 1986 In-Container Oewater1ng &
S0l1d1f1cat1on System (MOSS)
Modified Portland November, 1986 Cement (MPC-1) and Portable Mixing Station Solidi ff cat1 on Quick Dry Process for March, 1988 Dewatering of Bead Resin and Filter Sludge
,1 TOPICAL REPORT REVIEW STATUS
SUMMARY
AttactWlent 6 IN 89-27 March 8, 1989 Page 3 of 3 FOR RADWASTE VOLUME REDUCTION SYSTEMS (CONTINUED)
Office of Nuclear Reactor Regulation, January 1989 Acceptance Vendor Reeort No.
Title Date Duratek Corporation D-EVR/HED-1
. Enhanced Volume Reductton/
Heat Enhanced Dewater1ng
- August, 1988 System for Treatment of Nuclear Power Reactor Waste L1qu1ds Ch~Nuclear RDS-25506-01 RDS-1000 Radioactive W;ste October, 1988 Systems, Inc.
Dewater1ng System Nuclear Packaging, TP-03 011 So11d1fication System Under Review Inc.
Pacific Nuclear TP-04 Portable Solidification Under Review Systems, Inc.
System Pacific Nuclear.
TP-05 Radwaste S0Hd1f1cat1on Under Review Systems, Inc.
System Nuclear Packaging, TP:-06 11Env1ronstone" Cement Under Review Inc.
Encapsulation of Solid Radioactive Materials Note:
All reports except,those identified with an asterisk provide generic (not plant-specific) process control procedures or programs
- 1-e LIST OF RECEIITI.Y I.
NRC lllfONTIOII NOTICES fnforMt10II b1t1 of llottc1 lo.
SullJtct luu1nu 119*2' I111t,-iit Atr Supply to l/7/89 S1f1~-.. l1tac1 (qutpillllt 99.zs Un11t~orf11d Transfer of
°'r11e"II t p or COIi tro I of lfc1111N Acthttftl l/7/H 89-24 lklclqr Crfttc, lley S1f1~
l/6/119 et-Zl En*f-11t1l Q111llffc1tfon 3/3/llt of Lttco.i-v,.. CIR S.rf11 E lectrtc!! I c-tor1 89-22 Q1111tt0111l>l1 C1rttffcatt011 l/l/llt of F11t1111r1 89-21 c~..... In Plf'fOl'IIIIIICI Clllr1ct1r11tlc1 of 11e11,11111-2/27/llt Cllt Cln:11ft lreeltrs 118-73, D t...c t1 on-lltplndtnt LIi
- 2/27/0 Sllpp 1-.wt 1 Cllar1ct.rt1ttc1 of C111t111-
- nt Pllr91 V1hn 89-20 Ill Id F111Ul"H 111 I PW, 2/24/H of l),P011-J1ck1on ~1911 DL
- 0~1tt119 Ltc111111 CP
- Contructton P11"11tt
- UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE. $300 M1rcll 8, !Mt P19e I of I Il1u11111 to A 11 11o ldert of OU or CP1 for 111c l11r power r11ctors.
All U.S. IIIIC ICllll'CI, byprodllct, allf 1pecf1l 1111cl11r *tartal lfeftMel.
All fuel eycl*
I fCIIIINI lllf otller lfCltllNI poUIU1*1
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- 11.,,11t1tt11 of s~ct1l 111cl11r
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A 11 llo lcllrs of Cll.1 Dr CPI for wcl11r
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A I I llolNrt of 01.1 or c,, for 1111cl11r
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All llol..,.1 of Ills or CPI for IIIIC l11r si-r rMctor1.
All llolNN of 01.1 or Ch fw IIIClNP
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,tlllT CL.AU MAIL
,OITAOI IP,u1,AID USNIIC JtfllMIT No. G"'7