Information Notice 1989-27, Limitations on the Use of Waste Forms and High Integrity Containers for the Disposal of Low-Level Radioactive Waste
UNITED STATES
NUCLEAR REGULATORY COMMISSION
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 FORMS 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 forms (WFs) that contain
Class B and/or Class C low-level waste. The actions pertain to completion by
the NRC Office of Nuclear Material Safety and Safeguards (NMSS) of reviews of
vendor topical reports (TRs) on waste forms containing stabilized low level
wastes or on 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 summary for applicability to their activities and consider actions, as
appropriate, to avoid problems in disposing of certain waste streams.
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 B and Class C low-level waste
from reactor waste streams, from fuel cycle facilities or from certain by-product
materials waste streams. The solidification media for the waste forms typically
have consisted of cement, cement/gypsum, polymer or bitumen. The HIC materials
are typically iron-chromium-nickel alloys (i.e.; ferralium or austenitic stainless
steels), polyethylene-impregnated concrete, polyethylene, fiberglass/polyethylene
or coated carbon steel (please refer to the status summary in Attachment 1).
NRC reviews of vendor topical reports on solidified 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.
(7803020165 V4
IN 89-27 March 8, 1989 Approvals of stabilization media and HICs are limited to certain waste concen- trations or to certain waste streams which are stated in the TER and the letter
of transmittal. Thus, not all waste concentrations or waste streams in the
original TRs have been approved. These restrictions or limitations could affect
the ability of licensees to dispose of certain wastes. An example of an approved
stabilization medium (i.e., waste form) is 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 to a licensed collector and any licensed waste
processor who treats or repackages wastes are reminded that they must 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)(1) and (f)(3),
respectively, of 10 CFR 20.311, where it is indicated that a licensee shall
prepare all wastes so that the waste is 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 B and Class C
waste stability requirements of 10 CFR 61.56(b) is to process the waste in 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 would provide a "central" review of TRs that would be applicable for
all the disposal sites. Before the 1983 agreement the State of South Carolina
had issued ten Certificates of Compliance (Cs of c5 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 already been issued a C of C.
For such HICs, revocation of a C of C would take place only if a problem were
identified or if new information indicated that the HICs would not meet the
- "1Agreement State" means 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 acceptance criteria. For new HICs that were described in TRs submitted to the
NRC, the States would not issue Cs of C until the review had been completed by
the NRC; it should be noted, however, that periodic temporary approvals or
"variances" for limited quantities of certain types of HICs have been granted
by the State of Washington. For solidification processes, those processors
who submitted information 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, and Beatty can be found in Attachments 3, 4, and 5, respec- tively. Solidification media and high integrity containers shown in Attachment 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 meeting 10 CFR Part 61 requirements for waste form stability, unless
special provisions are provided at the disposal site, involves the use of high
density polyethylene (HDPE) high integrity containers. As indicated in Attach- ment 1, such containers, as described in topical reports submitted by three
vendors (Docket Nos. W14-18, 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 is shown that (beginning in 1981) several
HDPE containers have been issued Certificates of Compliance. Those containers
continue to be accepted for disposal at the Barnwell site "on an interim basis"
while South Carolina implements special provisions for disposal beginning
April 1, 1989. NRC-licensed waste generators who wish to use polyethylene
containers for the disposal of Class B and Class C wastes and who must comply
with the provisions of 10 CFR 20.311(d) should either (1) place and ship the
polyethylene container in an approved high integrity container (see Attachment 1 for a list of NRC-approved HICs) or (2) obtain assurance and documentation from
the disposal site operator that structural stability consistent with Part 61 requirements will be provided at the site. For example, stability requirements
,ay be met by placing the waste in an approved concrete container or structure
that provides stability after disposal. The State of South Carolina has author- ized the Barnwell Disposal Site Operator to receive class B & C waste in HDPE/HICS
for disposal in concrete overpacks. Waste generators desiring to pursue any of
these options should contact the facility operator for procedural details.
Accepted Stabilization Procedures -
Licensees carn ensure that Class Band/or Class C low-level wastes will be
accepted for burial at a disposal site by doing one of the following:
a. solidifying the waste into a form that is shown in the table in
Attachment 1 as "approved" or "under review" by the NRC and which
is accepted for disposal on an interim or final basis by the sited
State;
IN 89-27 March 8, 1989 b. placing the waste in a high integrity container (HIC) that
irn the table in Attachment 1 as "approved" by the NRC and is shown
a Certificate of Compliance or other State Approval document, for which
appropriate, has been issued; as
c. solidifying the waste into a form (i.e., using a Stabilization
that has been approved by the States of Nevada, South Medium)
Carolina, or
Washington for burial at the Beatty, Barnwell, or Hanford
appropriate (see Attachments 3, 4 and 5); sites, as
d. placing the waste in a HIC that has been approved by the
Nevada or for which a Certificate of Compliance has been State of
the States of South Carolina or Washington for burial at the issued by
Barnwell, and Hanford sites, as appropriate (see Attachments Beatty, and 5). 3, 4 The following paragraphs discuss specific issues related
waste forms and process control procedures. to the stability of
Maty reactor licensees are required to process wastes only
the plant-specific process control program (PCP). Generic in accordance with
process control procedures or programs are addressed in TRs (not plant-specific)
reviewed by NRC's Office of Nuclear Reactor Regulation (NRR),that are also
in Attachment 6. A summary of topical reports for radwaste except as noted
systems that NRR has approved or has under review is presented volume reduction
in Attachment 6.
Variances in Processing Parameters -
Some mixtures of wastes and solidification agents may react
another. These reactions may not be noticeable during the adversely with one
formed before the actual solidification occurs; therefore, specimen tests per- be alert to variances in solidification parameters specifiedit is important to
increasing temperature of the mixture and reduced amount by PCPs, such as
of solidification agent
required to fill the liner or other container. An example
a licensee either operated outside the bounds of the technical of a situation where
(TER) or mixed waste streams of questionable or unknown compatibilityevaluation report
in Information Notice No. 88-08, "Chemical Reactions with is described
Solidification Agents", March 14, 1988. Radioactive Waste
Cement-Solidified Waste Problems -
The problem identified in Information Notice No. 88-08 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 cement-solidified low-level waste. Such mishaps include but are not limited
to waste forms 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
in 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 B and C
low-level radioactive wastes within the boundary conditions, established 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-solidified 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-term 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 format 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 solidification
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 limitations on use of solidified
media and HICs. To assist the waste generators and others in this regard, updates of the statusof NRC TR reviews will 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.
IN 89-27 March 8, 1989 No specific action or written response is required by this information notice.
A summary of topical report reviews is presented in Attachment 1. If you have
any questions regarding this information notice, please contact the technical
contacts listed below or the Regional Administrator of the appropriate regional
office. A list of recent information notices is shown in Attachment 7 for
background information.
t'John T. Greeves, Acting Director
Division of Low-Level Waste Management
and Decommissioning, NMSS
Technical Contacts: Michael Tokar, NMSS
(301) 492-0590
Charles Nichols, NRR
(301) 492-0854 Attachments:
1. Topical Report Review Status Summary, Solidified Waste Form and
High Integrity Containers (HICs)
2. Example of Approved Stabilization Medium and Limitations on
Approved Waste Streams
3. List of HICs and Stabilization Media Currently Accepted at Beatty
4. List of HICs and Stabilization Media Currently Accepted at Barnwell
5. List of HICs and Stabilization Media Currently Accepted at Hanford
6. Topical Report Review Status Summary for Radwaste Volume Reduction
Systems
7. List of Recently Issued NRC Information Notices
Attachment-1 IN 89-27 March 8, 1989 TOPICAL REPORT REVIEW STATUS SUMMARY
SOLIDIFIED WASTE FORM AND HIGH INTEGRITY TAINERS (HICs)
JANUARY 5, 1989 Office of Nuclear Material Safety and Safeguards
Vendor Docket No. Disposition
Waste Chem WM-90** So~lidification (bitumen) Approved.
General Electric WM-88 Solidification (polymer) Approved.
DOW WM-82** Solidification (polymer) Approved.
Chichibu 1*1-81 HIC (poly impreg/concrete) Approved.
Nuclear Packaging WM-45 HIC (ferraliuum/FL-50) Approved.
Nuclear Packaging WM-85** HIC (ferralium/family) Approved.
LN Technologies WM- 93** HIC (stainless/poly) Approved.
Chem-Nuclear W1- 18** HIC (polyethylene) Not Approved.
Hittman WM-80** HIC (polyethylene) qNot Approved.
TFC Nuclear WM-~76** HIC (polyethylene) Not Approved.
U.S. Gypsum WM-51** Solidification (gypsum)* Not Approved.
AlI (U.S.Ecology) WM-91** Solidification (bitumen) Discontinued.
VIKEM WM-13 Solidification/oil (cement) Discontinued.
Stock WM-92** Solidification (cement) Discontinued.
Nuclear Packaging WM- 71 Solid/Encap (cement/gypsum) Withdrawn.
Chem-Nuclear Wm- 19.** Solidification (cement Withdrawn.
Chem-Nuclear WM-96** Solidification (cement Withdrawn.
Hittman Solidification (SG-95) Withdrawn.
Nuclear Packaging WM-87** HIC (316-stainless/SDS) Withdrawn.
LN Technologies WM-57 HIC (polyethylene) Withdrawn.
Chem-Nuclear WM-47 HIC (fiberglass/poly) Withdrawn.
Chem-Nuclear WM-101 Solidification (cement #1) Under review.
Chem-Nuclear WM-97 Solidification (cement #2) Under review.
Chem-Nuclear WM-98 Solidification (cement #3) Under review.
LN Technologies WM-20 Solidification (cement) Under review.
LN Technologies WM-99 Solidification (cement/decon) Under review.
Hittman WM-46 -Solidification (cement) Under review.
ATI (U.S. Ecology) WM- 100- Solidification (bitumen) Under review.
BondIco WM-94 HIC (fiberglass/poly) Under review.
Babcock & Wilcox WM-95 HIC (coated carbon steel) Under review.
Had been approved for single waste stream for one year ending March 3, 1989.
Actions completed in Calendar Year 1988.
\a_, Attachment 2 IN 89-27 March 8, 1989 EXAMPLE OF APPROVED STABILIZATION MEDIUM AND LIMITATIONS ON
APPROVED WASTE STREAMS
-
-
VENDOR TYPE
Waste Chem Corporation Solidification Media
(ASTM-D-312 Type III
oxidized bitumen)
DOCKET
Approved For:
WASTE STREAM(s) LIMITATION (s)
Bead Resin Waste Forms must
Precoat Filter Cake with Powdered Resin be prepared in
Precoat Filter Cake with Diatomaceous Earth Accordance with
Evaporator Concentrates - Neutralization Waste Process Control
Evaporator Concentrates - Floor Drain Program (PCP)
Evaporator Concentrates
Decontamination Waste Waste Form in
Mixed Resin and Filter Cake Waste 55-Gallon Drum or
approved HIC
CONCENTRATION
Maximum waste loadings are as stated in Section A-3.3 of the WasteChem Topical
Report, VRS-002, dated August 1987 or in Table I of Appendix A of the NRC
dated January 22, 1988.
-Attachment 3 IN 89-27 March 8, 1989 LIST OF HICs AND STABILIZATION MEDIA
CURRENTLY ACCEPTED AT BEATTY
HICs Package Identification
Manufacturer Number
Pacific Nuclear DSHS-HIC-TMI-01 Nuclear Packaging DSHS-HIC-EA-50
Chichibu Cement DSHS-HIC-SFPIC200L
Chichibu Cement DSHS-HIC-SfPIC400L
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
10. Other solidification media and processes which have been approved by
U. S. Nuclear Regulatory Commission and/or the State as meeting
waste form 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 in a fifty-five
gallon drum containing concrete, shall have a formulated compressive
strength equal to or greater than 2500 psi.
Attachment 4 IN 89-27 March 8, 1989 LIST OF HICs AND STABILIZATION MEDIA
CURRENTLY ACCEPTED AT BARNWELL
HIC Certificates of Compliance
Issued to Issued what Issued when
Adwin Equipment Company 55-gallon HIC 05/29/84 Chem-Nuclear HDPE HICs (x 14) 05/28/81 Chem-Nuclear FRP HIC 02/23/82 Chem-Nuclear Overpack HICs (x3) 04/08/83 Philadelphia Electric Comp. PECO-HIC-1 09/28/81 Hittman Radlok-55 HIC 06/17/82 Hittman Radlok-100 HIC 06/17/82 Hittuan Radlok-200 HIC 05/05/83 Hittman Radlok-500 HIC 09/31/85 LN Technologies Barrier-55 HIC 09/01/83 TFC NUHIC-120 HIC 11/01/83 NUPAC HDPE 142 HIC 08/20/84 NUPAC FL-50 HIC 09/26/85 Chichibu Concrete HICs (x2) 08/12/86 Vermont Yankee HDPE HIC 10/10/83 Approved Stabilization Media*
Vinyl Ester Styrene
Cement
- Bitumen
- Processes shall meet and have been evaluated in 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 are necessary for the disposal
of this waste form.
Attachment 5 IN 89-27 March 8, 1989 LIST OF HICs AND STABILIZATION MEDIA
CURRENTLY ACCEPTED AT HANFORD
HIC Certificates Of Compliance (C of C)
Package
Identification
C of C Number Manufacturer Number
WN-HIC-01 Pacific- Nuclear DSHS-HIC-TMI-O1 WN-HIC-02 Nuclear Packaging DSHS-HIC-EA-50
WN-HIC-03 Chichibu Cement DSHS-HIC-SFPIC 200L
WN-HIC-04 Chichibu Cement DSHS-HIC-SFPIC 400L
WN-HIC-05 Nuclear Packaging DSHS-HIC-EA 142A
WN-HIC-06 Nuclear Packaging DSHS-HIC-EA 50A
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 50C
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
Attachment 5 IN 89-27 March 8, 1989 LIST OF HICs AND STABILIZATION MEDIA
CURRENTLY ACCEPTED AT HANFORD (CONTINUED)
Approved Stabilization Media *
Aztech (General Electric)
Bitumen** (ATI and Waste Chem)
Chem-Nuclear Cement
Dow Media (Vinyl Ester Styrene)
Envirostone (U.S. Gypsum Cement)
Westinghouse-LN Technologles Cement
Stock Equipment Cement
Hittman Cement
Concrete***
- Only those stabilization media which have been evaluated or are in the
process of being evaluated and are used with the stability guidance
requirements of the NRC "Technical Position on Waste Form" or are
specifically approved by the State are considered acceptable
stabilization 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 form 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 in a fifty-five
gallon drum containing concrete, shall have a formulated compressive
strength equal to or greater than 2500 psi.
Attachment 6 IN 89-27 March 8, 1989 TOPICAL REPORT REVIEW STATUS SUMMARY
FOR RADWASTE VOLUME REDUCTION SYSTEMS
Office of Nuclear Reactor Regulation, January 1989 Acceptance
Vendor Report No. Title Date
- Aerojet Energy AECC-1 Fluid Bed Dryer
Conversion Co. December, 1975 Hittman Nuclear & HN-R1109-A, Radwaste Solidification
Development Corp. April, 1978 Revision 4 System (Cement)
Werner & Pflelderer WPC-VRS-001, Radwaste Volume Reduction
Corporation April, 1978 Revision I & Solidification System
Dow Chemical Company DNS-RSS-001 The Dow System for Solid- June, 1980
ification of Low-Level
Radioactive Waste from
Nuclear Power Plants
ATCOR Engineered ATC- 132A Radwaste Solidification
Systems, Inc. September, 1981 System
- Newport News EI/NNI-77-7 RWR-1 Radwaste Volume
Industrial Corp. October, 1982 Reduction System
Chem-Nuclear CNSI-2 Mobile Cement Solidifi- Systems, Inc. March, 1983
(4313-01354-01) cation System
- JGC Corporation JGC-TR-001 The Drum Mixer Process July, 1983 for Volume Reduction
& Solidification
- Aerojet Energy AECC-4 Mobile Volume Reduction
Conversion Company October, 1984 System
- Aerojet Energy AECC-2' Radioactive Waste Volume
Conversion Company November, 1984 Reduction System
Associated Technologies ATI-VR-O 01 ATI Volume Reduction
Incorporated April, 1985 and Bitumen
Solidification System
NUS Process Services PS-53-0378 Radwaste Solidification
Corporation May, 1985 System
Attachment 6 IN 89-27 March 8, 1989 TOPICAL REPORT REVIEW STATUS SUMMARY
FOR RADWASTE VOLUME REDUCTION SYSTEMS (CONTINUED)
Office of Nuclear Reactor Regulations, January 1989 Acceptance
Vendor Report No. Title Date
Chem-Nuclear CNSI-DW-11118-01 CNSI Dewatering Control June, 1985 Systems, Inc. Process Containers
ATCOR Engineered ATC-8019-1 ATCOR AVRS-80 Volume July, 1985 Systems, Inc. Reduction Process
Nuclear Packaging, TP-02 Nuclear Packaging, Inc. September, 1985 Inc. Dewatering System
General Electric NEDE-30878 Transportable Modular December, 1985 AZTECH Plant
- Koch Process KPS-1 VR-System 350 Low-Level March, 1986 Systems, Inc. Radwaste Volume Reduction
System
Associated Tech., ATI-VR-OO1 ATI Transportable Vol. April, 1986 Incorporated Supplement 1 Reduction & Bitumen Solid- ification System (.TVR-111)
UNC Nuclear UNC-S 8000 UNC Portland Cem./Sodium August, 1986 Industries Silicate Radwaste Solid- ification Systems
- Aerojet Energy AECC-3 Radioactive Waste Volume August, 1986 Conversion Company Reduction System
Westinghouse STD-R-05-01 1 Hittman Mobile October, 1986 Hittman Nuclear, In-Container Dewatering &
Incorporated Solidification System (MDSS)
Bartlett Nuclear, BN- 1 Modified Portland November, 1986 Incorporated Cement (MPC-1) and
Portable Mixing Station
Solidification
Stock Equipment SRS-003 Quick Dry Process for March, 1988 Company Dewatering of Bead Resin
and Filter Sludge
Attachment 6 IN 89-27 March 8, 1989 TOPICAL REPORT REVIEW STATUS SUMMARY
FOR RADWASTE VOLUME REDUCTION SYSTEMS (CONTINUED)
Office of Nuclear Reactor Regulation, January 1989 Acceptance
Vendor Report No. Title Date
Duratek Corporation D-EVR/HED-1 Enhanced Volume Reduction! August, 1988 Heat Enhanced Dewatering
System for Treatment of
Nuclear Power Reactor
Waste Liquids
Chem-Nuclear RDS-25506-01 RDS-1000 Radioactive Waste October, 1988 Systems, Inc. Dewatering System
Nuclear Packaging, TP-03 Oil Solidification System Under Review
Inc.
Pacific Nuclear TP-04 Portable Solidification Under Review
Systems, Inc. System
Pacific Nuclear TP-05 Radwaste Solidification Under Review
Systems, Inc. System
Nuclear Packaging, TP-06 "Environstone" 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.
reh 8, 198S
__rago I of I
LIST OF RECENTLY
ISSUED
NRC INFORMIATION
NOTICES
Informaton Date of
Notice no. SubJect Issuae t Issued to
Isnnc Iss_.to
7-49 Infstrument Air Supply to 3/7/89 All holders of OLs
Safety-Related Equipment or CPs for nuclear
power reactors.
89-25 Unauthorized Transfer of 3/7/89 All U.S. NRCsource.
Ownership or Control of byproduct, and special
Licensed Activities nuclear material
licensees.
89-24 Nuclear Criticality Safety 3/6/89 All fuel cycle
licensees and other
licensees possessing
more than critical
mess quantities of
special nuclear
meterial.
89-23 Environmental Qualification 3/3/89 All holders of OLs
of Litton-Yean CIR Series or CPs for nuclear
Electricsl Connectors power reactors.
89-22 Questionable Certification 3/3/89 All holders of OLs
of Fasteners or CPs for nuclear
power reactors.
89-21 Changes in Performance 2/27/89 All holders of OLs
Characteristics of Molded- or CPs for nuclear
Case Circuit Breakers power reactors.
88-73, Direction-Dependent Leek 2/27/89 All holders of OLs
Supplement 1 Characteristics of Contain- or CPs for nuclear
ment Purge Valves power reactors.
89-20 Weld Failures In a Pump 2/24/89 All holders of OLs
of Byron-Jackson Design or CPs for nuclear
power reactors.
OL Operating License
CP- Construct1on Perrmt
UNITED STATES
FIRST CLASS MAIL
NUCLEAR REGULATORY COMMISSION POSTAGE & FEES PAID
WASHINGTON, D.C. 20555 USNRC
PERMIT No. G-67 OFFICIAL BUSINESS
PENALTY FOR PRIVATE USE, S300
IN 89-27 March 8, 1989 No specific action or written response is required by this information notice.
A summary of topical report reviews is presented in Attachment 1. If you have
any questions regarding this information notice, please contact the technical
contacts listed below or the Regional Administrator of the appropriate regional
office. A list of recent information notices is shown in Attachment 7 for
background information.
John T. Greeves, Acting Director
Division of Low-Level Waste Management
and Decommissioning, NMSS
Technical Contacts: Michael Tokar, NMSS
(301) 492-0590
Charles Nichols, NRR
(301) 492-0854 Attachments:
1. Topical Report Review Status Summary, Solidified Waste Form and
High Integrity Containers (HICs)
2. Example of Approved Stabilization Medium and Limitations on
Approved Waste Streams
3. List of HICs and Stabilization Media Currently Accepted at Beatty
4. List of HICs and Stabilization Media Currently Accepted at Barnwell
5. List of HICs and Stabilization Media Currently Accepted at Hanford
6. Topical Report Review Status Summary for Radwaste Volume Reduction
Systems
7. List of Recently Issued NRC Information Notices
Distribution: Central File 202.2 NMSS rf LLTB rf EWick,LLTB MTokar,LLTB
JSurneier,LLTB JGreeves,LLWM RCunningham,NMSS VY4iller,GA/SLITP
CRossi,NRR/DOEA MBell,LLRB PLohaus LLOB JCraig, NRR/SPLB
RBernero, NMSS
PDR/NUDOCS Yes Z7 D /12y
ACNW Yes No £7 SUBJECT ABSTRACT:
- SEE PREVIOUS CONCURRENCE
OFC :LLTB* :LLTB* :LLTB* :NRR/SPLB* LLWM* :NMSS * :
_- _________________- _- _______- ________-__-
_________________________________
NAME:Ek'ick/lj :MTokar :JSurmieier:JCraig :JGreeves:RBernero :
-________-___________________-___________
DATE:02/24/89 :02/24/89 :02/24/89 :02/24/89 :02/24/89:03/01/89 :
OFFICIAL RECORD COPY
IN 89- March 3, 1989 No specific action or written response is required by this information notice.
A summary of topical report reviews is presented in Attachment 1. If you have
any questions regarding this information notice, please contact the technical
contacts listed below or the Regional Administrator of the appropriate regional
office. A list of recent information notices is shown in Attachment 7 for
background information.
/f
John T./Greeves, Acting Director
Divis)6n of Low-Level Waste Management
a7 Decommissioning, NMSS
Technical Contacts: Michael Tokar, NMSS Charles Nichols, NRR
(301) 492-0590 (301) 492-0854 Attachments: 1. Topical Rep t Review Status Summary, Solidified aste Form and High
Integrity Containers (HICs)
2. Example f Approved Stabilization Medium and
Limita, ons on Approved Waste Streams
3. List 9f HICs and Stabilization Media Currently
Accepted at Beatty
4. Lis of HICs and Stabilization Media Currently
Ac epted at Barnwell
5. Lst of HICs and Stabilization Media Currently
ccepted at Hanford
6. opical Report Review Status Sunmary for Radwaste
Volume Reduction Systems
7. List of Recently Issued NRC Information Notices
Distribution:
NMi rf- LLTB rf EWick,LLTB MTokar,LLTB
JSurmeier,LLTB JGreeves,LLWM RCunningham,NMSS YMiller,GA/SLITP
.1LLRR
CRossi,NRR/DOEA MRP1 ., _ PLohaus-LLOR
, ___
.. __
- SEE PREVIOUS CONCURRENCE
OFC :LLTB* :LLTB* :LLTB* :NRR/SPLB*:LL :LLWM :NMSS
___________
NAME:EWick/lj :MTokar :JSurmeier:JCraig _: s: : t'gi s o
- ---------
DATE:02/24/89 :02/24/89 :02/24/89 :02/24/89 : Z?'/89: / /89 : 3 / 1 /89 OFFICIAL RECORD COPY
IN 89- March 3, 1989 Attachments: 1. Topical Report Review Status Summary, Solidified Waste Form and High
Integrity Containers (HICs)
2. Example of Approved Stabilization Medium and
Limitations on Approved Waste Streams
3. List of HICs and Stabilization Media Currently
Accepted at Beatty
4\ List of HICs and Stabilization Media Currently
Accepted at Barnwell
5.\List of HICs and Stabilization Media Currently
Accepted at Hanford
6. Tical Report Review Status Summary for Radwa! ste
Vo me Reduction Systems
7. List of Recently Issued NRC Information Notice!5 Distribution:
NMSS rf LLTB rf EWick,LLTB MTokar,LLTB
JSurmeier,LLTB JGreeves,LLWM RCunningham,NMSS VMiller,GA/SLITP
CRossi,NRR/DOEA MBell,LLRB PLohaus,LLOB
1-11 t(\
OFC :LLTB U:LLM LTJ R :
. L :LLWM :NMSS
NAME:EWick/lj :MTokar :JSu7ier:JCr JGreeves: \
DATE:Az/;Z~/s9 :.212-989 :&/lZ#89 a j\19 : / /89: / /89 :/ /89 OFFICIAL RECORD COPY