ML20133P811: Difference between revisions

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                    o                                  UMITED STATES
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                        'o                 WUCLEAR REGULATORY COMMISSION
UMITED STATES
        #Y           7 ,^                               REGloN 11
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                      I
WUCLEAR REGULATORY COMMISSION
        k*- .k       "'' t
"
                                                  101 MARIETTA STREET.N.W.
#Y
                                                  ATLANTA, GEORGI A 30323
7 ,^
              *%d     o                                                                           \
REGloN 11
              .....                                     JUI. 2 9 pg
k .k
          Report Nos.:       70-824/85-05, 50-013/85-01
I
          Licensee: Babcock and Wilcox Company
101 MARIETTA STREET.N.W.
                          Lynchburg Research Center
*-
                          Lynchburg, VA 24505
"'' t
          Docket Nos.:       70-824 and 50-013                           License No.: SNM-778 and
ATLANTA, GEORGI A 30323
                                                                                        CX-10
*%d
          Facility Name: Lynchburg Research Center
o
          Inspection Conducted: June 10-14, 1985
\\
          Inspector:         e/N1
JUI. 2 9 pg
                  y R. H. AlbrigTt
.....
                                                                                        7//s/35
Report Nos.:
                                                                                        Date signed
70-824/85-05, 50-013/85-01
          Approved by: M                                                               7 / /t' h5
Licensee: Babcock and Wilcox Company
                            C. M. Hc'sey, Sect ion Chief                                 Date Signed
Lynchburg Research Center
                            DivisionofRadia(tionSafetyandSafeguards
Lynchburg, VA 24505
                                                        SUMMARY
Docket Nos.:
          Scope: This routine, unannounced inspection entailed 17 inspector-hours on site
70-824 and 50-013
          in the area of transportation of radioactive material.
License No.:
          Results:       Three violations - Failure to package low specific activity (LSA)
SNM-778 and
          radioactive material in a strong tight package; failure to ensure that the
CX-10
          closure device on a package of Fissile Class II material was free of defects
Facility Name: Lynchburg Research Center
          prior to shipment and failure to ship Fissile Class II material in a tested,
Inspection Conducted: June 10-14, 1985
          approved package; failure to label packages of radioactive material as required
Inspector:
          by the burial facility license.
e/N1
7//s/35
y R. H. AlbrigTt
Date signed
Approved by: M
7 / /t' h5
C. M. Hc'sey, Sect ion Chief
Date Signed
DivisionofRadia(tionSafetyandSafeguards
SUMMARY
Scope: This routine, unannounced inspection entailed 17 inspector-hours on site
in the area of transportation of radioactive material.
Results:
Three violations - Failure to package low specific activity (LSA)
radioactive material in a strong tight package; failure to ensure that the
closure device on a package of Fissile Class II material was free of defects
prior to shipment and failure to ship Fissile Class II material in a tested,
approved package; failure to label packages of radioactive material as required
by the burial facility license.
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      8508140494 850729
8508140494 850729
      PDR       ADOCK 05000013
PDR
      O                         PDR     m
ADOCK 05000013
                                '
O
                                                                                            \
PDR
m
'
\\


,.                                                           - -
,.
  .-
- -
                                            2
.-
                                      REPORT DETAILS
2
    1. Persons Contacted
REPORT DETAILS
        Licensee Employees
1.
      *A. E. Wehrmeister, Manager, System Development Laboratory
Persons Contacted
      *J. P. Doran, Manager, Accounting and Administrative Services
Licensee Employees
      *G. Hoovier, Manager, Building A Decommissioning Project
*A. E. Wehrmeister, Manager, System Development Laboratory
      *J. W. Cure, Supervisor, Health and Safety
*J. P. Doran, Manager, Accounting and Administrative Services
      *A. Olsen, Senior License Administrator
*G. Hoovier, Manager, Building A Decommissioning Project
        D. Harris, Health Physics Technician
*J. W. Cure, Supervisor, Health and Safety
      * Attended Exit Interview.
*A. Olsen, Senior License Administrator
    2. Exit Meeting
D. Harris, Health Physics Technician
        The inspection scope and findings were summarized on June 14, 1985, with
* Attended Exit Interview.
        those persons indicated in paragraph 1 above. The apparent violation of
2.
        10 CFR 71.87 for shipment of a package with a crack under a closure bracket,
Exit Meeting
        violation of 10 CFR 70.42 for transferring special nuclear material to a
The inspection scope and findings were summarized on June 14, 1985, with
        land disposal facility without the labels required by receiver's license and
those persons indicated in paragraph 1 above.
        violation of 10 CFR 71.5 for the shipment of a package of LSA radioactive
The apparent violation of
        material which failed to meet the strong tight container requirement were
10 CFR 71.87 for shipment of a package with a crack under a closure bracket,
        discussed in detail. Licensee management acknowledged the violations.
violation of 10 CFR 70.42 for transferring special nuclear material to a
        The licensee was notified during a telephone conversation on June 19, 1985,
land disposal facility without the labels required by receiver's license and
        between J. B. Kahle of this office and A. Olsen of the licensee's staff that
violation of 10 CFR 71.5 for the shipment of a package of LSA radioactive
        failure to choose a package that was proper for the contents was another
material which failed to meet the strong tight container requirement were
        example of a violation of 10 CFR 71.87.
discussed in detail.
        The licensee did not identify as proprietary any of the materials provided
Licensee management acknowledged the violations.
        to or reviewed by the inspector during this inspection.
The licensee was notified during a telephone conversation on June 19, 1985,
  3.   Licensee Action of Previous Enforcement Matters
between J. B. Kahle of this office and A. Olsen of the licensee's staff that
        This subject was not addressed in the inspection.
failure to choose a package that was proper for the contents was another
  4.   Transportation of Radioactive Material (86740)
example of a violation of 10 CFR 71.87.
        On May 29, 1985, NRC Region II received a copy of a letter dated May 20,
The licensee did not identify as proprietary any of the materials provided
        1985, from the State of Washington to the B&W Lynchburg Research Center.
to or reviewed by the inspector during this inspection.
        The letter described two violations in shipment No. LRC-23. The first
3.
        violation concerned a hole in a drum of LSA radioactive material in
Licensee Action of Previous Enforcement Matters
        violation of the strong tight package requirement of 49 CFR 173.425. The
This subject was not addressed in the inspection.
        second violation concerned the failure to meet requirements of the U.S.
4.
        Ecology land disposal facility license by affixing the correct number of
Transportation of Radioactive Material (86740)
        labels to each package.
On May 29, 1985, NRC Region II received a copy of a letter dated May 20,
1985, from the State of Washington to the B&W Lynchburg Research Center.
The letter described two violations in shipment No. LRC-23.
The first
violation concerned a hole in a drum of LSA radioactive material in
violation of the strong tight package requirement of 49 CFR 173.425.
The
second violation concerned the failure to meet requirements of the U.S.
Ecology land disposal facility license by affixing the correct number of
labels to each package.


  .-
.-
        ,
,
      ,.
,.
                                                  3
3
          On May 1,1985, the licensee made shipment No. LRC-23 to the U.S. Ecology
On May 1,1985, the licensee made shipment No. LRC-23 to the U.S. Ecology
          land disposal facility at Richland Washington. While unloading the shipment
land disposal facility at Richland Washington. While unloading the shipment
          of drums on May 6, 1985, disposal site personnel observed a hole in the side
of drums on May 6, 1985, disposal site personnel observed a hole in the side
          of drum number 4740. The waste manifest described the contents of the drum
of drum number 4740. The waste manifest described the contents of the drum
          as uranium oxides on lab trash and equipment. The radionuclide content
as uranium oxides on lab trash and equipment.
          measured was Uranium-234 at 0.03 mil 11 curies, Uranium-235 at 0.002
The radionuclide content
          millicuries, Uranium-236 at 0.0004 millicuries, and Uranium-238 at 0.01
measured was Uranium-234 at 0.03 mil 11 curies, Uranium-235 at 0.002
          millicuries. The drum was listed as Fissile Exempt and labeled Radioactive
millicuries, Uranium-236 at 0.0004 millicuries, and Uranium-238 at 0.01
          LSA. The licensee's investigation determined that shifting of a 32 pound
millicuries. The drum was listed as Fissile Exempt and labeled Radioactive
          metal object inside the container caused the hole. The inspector discussed,
LSA. The licensee's investigation determined that shifting of a 32 pound
          with the U.S. Ecology health physics (HP) technician who identified the hole
metal object inside the container caused the hole. The inspector discussed,
          in the drum, the details of the U.S. Ecology receipt of shipment No. LRC-23.
with the U.S. Ecology health physics (HP) technician who identified the hole
          The HP technician stated that the drum with the hole had not been moved from
in the drum, the details of the U.S. Ecology receipt of shipment No. LRC-23.
          its shipment position in the trailer before the hole was observed. The hole
The HP technician stated that the drum with the hole had not been moved from
          was observed after drums in front of this drum were removed while unloading
its shipment position in the trailer before the hole was observed. The hole
          the shipment. The metal object inside the drum which apparently shifted
was observed after drums in front of this drum were removed while unloading
          during transportation and caused the hole was protruding from the hole when
the shipment. The metal object inside the drum which apparently shifted
          observed by the HP technician.     It was determined that the hole had been
during transportation and caused the hole was protruding from the hole when
          punched through the wall of the Department of Transportation (DOT)
observed by the HP technician.
          Specification 17 H drum during transport. Surveys outside the hole did not
It was determined that the hole had been
          indicate leakage of radioactive material from the can.         The amount of
punched through the wall of the Department of Transportation (DOT)
          radioactive material inside the can would not have caused a significant
Specification 17 H drum during transport. Surveys outside the hole did not
          public health and safety problem if it had been released.
indicate leakage of radioactive material from the can.
          10 CFR 71.5(a) requires that licensees who transport licensed material
The amount of
          outside the confines of its place of use or delivers such material to a
radioactive material inside the can would not have caused a significant
          carrier for transport comply with the requirements of DOT regulations
public health and safety problem if it had been released.
          contained in 49 CFR Parts 170 through 189. 49 CFR 173.425 requires that LSA
10 CFR 71.5(a) requires that licensees who transport licensed material
          materials be shipped in a DOT specification 7A Type A package or a strong
outside the confines of its place of use or delivers such material to a
          tight package such that there will be no leakage of the package contents
carrier for transport comply with the requirements of DOT regulations
          during normal conditions of transport.       In discussions with licensee
contained in 49 CFR Parts 170 through 189. 49 CFR 173.425 requires that LSA
          representatives and reviews of shipping papers it was determined that three
materials be shipped in a DOT specification 7A Type A package or a strong
          licensee personnel observed the drum to be in good condition prior to
tight package such that there will be no leakage of the package contents
          transport.   No other drums were damaged.   Failure to ship LSA radioactive
during normal conditions of transport.
          material in a DOT Specification 7A Type A package or a strong tight package   ;
In discussions with licensee
                                        apparent violation of 10 CFR 71.5(a).
representatives and reviews of shipping papers it was determined that three
                                                                                          '
licensee personnel observed the drum to be in good condition prior to
          was    identified    as  an
transport.
          (70-824/85-05-01).
No other drums were damaged.
                                                                                          1
Failure to ship LSA radioactive
          10 CFR 20.301 prohibits the disposal of radioactive material except under
material in a DOT Specification 7A Type A package or a strong tight package
                                                                                          '
;
          specified conditions including _ transfer to an authorized recipient as
was
          provided in the regulations in Parts 30, 40, 60, 61, 70 or 72 of this
identified
          chapter, whichever is applicable.       10 CFR 70.42 states requirements that
as
          must be met prior to transferring special nuclear material (SNM).         One
an
          requirement is that SNM may be transferred to any person authorized to
apparent
          receive such SNM under terms of a specific license or a general license or
violation
          their equivalents issued by the Commission or an Agreement State. U.S.
of
          Ecology license, from the State of Washington, WN-1019-2, license condition
10 CFR
          27(k), requires that when waste is labeled with a DOT White I, Yellow II or
71.5(a).
          Yellow III label a waste classification label should appear next to or in
'
          close proximity to each DOT label . The license condition further requires       ,
(70-824/85-05-01).
          that when White I, Yellow II or Yellow III labels are required two of the
1
+.                                                                                         1
10 CFR 20.301 prohibits the disposal of radioactive material except under
'
specified conditions including _ transfer to an authorized recipient as
provided in the regulations in Parts 30, 40, 60, 61, 70 or 72 of this
chapter, whichever is applicable.
10 CFR 70.42 states requirements that
must be met prior to transferring special nuclear material (SNM).
One
requirement is that SNM may be transferred to any person authorized to
receive such SNM under terms of a specific license or a general license or
their equivalents issued by the Commission or an Agreement State.
U.S.
Ecology license, from the State of Washington, WN-1019-2, license condition
27(k), requires that when waste is labeled with a DOT White I, Yellow II or
Yellow III label a waste classification label should appear next to or in
close proximity to each DOT label . The license condition further requires
,
that when White I, Yellow II or Yellow III labels are required two of the
1
+.


                                                      _                                    _ _ _ _
  ,
                                                                                                    1
    .- *
                                              4
        specific labels must be displayed on each drum.              Land disposal site
        personnel observed that six drums in the LRC-23 shipment displayed two
        Yellow II labels.    However, only one waste classification label was affixed
        to each of the six drums.      Failure to comply with requirements of the
,
,
        receiver's license by not affixing the appropriate number of waste
_
_ _ _ _
*
.-
4
specific labels must be displayed on each drum.
Land disposal site
personnel observed that six drums in the LRC-23 shipment displayed two
Yellow II labels.
However, only one waste classification label was affixed
to each of the six drums.
Failure to comply with requirements of the
receiver's license by not affixing the appropriate number of waste
,
classification labels was identified as an apparent violation of 10 CFR
'
'
        classification labels was identified as an apparent violation of 10 CFR
i      70.42.    (70-824/85-05-03).
        10 CFR 71.87 requires that prior to each shipment of licensed material that
        certain requirements be met. These include ensuring that the package is
        prope for the contents to be shipped, that the package is in unimpaired
        physical condition except for superficial defects such as marks or dents and
        that each closure device of the packaging is properly installed and secured
        and free of defects.
        Six drums marked Fissile Class II in shipment LRC-23 were listed on the
        shipping papers as DOT specification 7A Type A packages. The quantity of
        SNM in the six drums ranged from '.7,02 grams (3E-2 milli-curies U-235) to
        25.92 grams (SE-2 milli-curies). The inspector reviewed the tests performed
        for the 55 gallon drum that was used to meet the DOT specification 7A Type A
        requirements. 49 CFR 173.465 specifies the tests that Type A packages must
        pass prior to use. Fissile Class II packaging, in addition to other Type A
        package tests, requires a free drop from a height of 0.3 meter (1 foot) on
        each corner. For cylindrical packagings, the 0.3 meter drop shall be onto
        each quarter of each rim. The test data review indicated that the corner
        drop test had not been performed. These drums were part of an exclusive use
        shipment in a closed transport vehicle.      These packages were not damaged
        during the shipment and no leakage of radioactive material occurred.
        Failure to perform the required drop test resulted in use of an improper
        package to ship Fissile Class II material. Failure to ship the Fissile
        Class II material in a proper package was identified as an apparent
        violation of 10 CFR 71.87.    (70-824/85-05-02).
        As a part of the decommissioning of the CX-10 reactor at the Lynchburg
        Research Center (LRC) the licensee disposed of the reactor's fuel rods by
        transfering them to Department of Energy (00E) facilities at Oak Ridge. The
        reactor had not been operated above one kilowatt.                  The fuel was
        approximately 2.5 percent enriched in U-235 and was considered unirradiated
        per the 00T definition in 49 CFR 173.403.        LRC transferred the fuel in
        containers covered by NRC Certificate of Compliance No. 9069.
        LRC refurbished the containers prior to use.            The first shipment of CX-10
        fuel arrived at the Oak Ridge National Laboratory (ORNL) on August 21, 1984.
        On arrival ORNL personnel discovered a crack in the outer skin of the
        outside container just beneath the horizontal weld on one of the lower
        ratchet binders. The crack did not affect package integrity. The ratchet
        binder is one of twelve primary closure devices. There are also twelve high
        strength latch pins which serve as secondary closure devices.                After
i
i
        receiving notification of this crack from ORNL, the licensee reviewed
70.42.
        photographs of the loaded packages taken prior to shipment and observed that
(70-824/85-05-03).
        the crack was evident prior to shipment.         The licensee, as corrective
10 CFR 71.87 requires that prior to each shipment of licensed material that
                    _
certain requirements be met. These include ensuring that the package is
                                    .             .     _ _ .     -         _.     - . __
prope for the contents to be shipped, that the package is in unimpaired
physical condition except for superficial defects such as marks or dents and
that each closure device of the packaging is properly installed and secured
and free of defects.
Six drums marked Fissile Class II in shipment LRC-23 were listed on the
shipping papers as DOT specification 7A Type A packages.
The quantity of
SNM in the six drums ranged from '.7,02 grams (3E-2 milli-curies U-235) to
25.92 grams (SE-2 milli-curies). The inspector reviewed the tests performed
for the 55 gallon drum that was used to meet the DOT specification 7A Type A
requirements. 49 CFR 173.465 specifies the tests that Type A packages must
pass prior to use. Fissile Class II packaging, in addition to other Type A
package tests, requires a free drop from a height of 0.3 meter (1 foot) on
each corner. For cylindrical packagings, the 0.3 meter drop shall be onto
each quarter of each rim.
The test data review indicated that the corner
drop test had not been performed. These drums were part of an exclusive use
shipment in a closed transport vehicle.
These packages were not damaged
during the shipment and no leakage of radioactive material occurred.
Failure to perform the required drop test resulted in use of an improper
package to ship Fissile Class II material. Failure to ship the Fissile
Class II material in a proper package was identified as an apparent
violation of 10 CFR 71.87.
(70-824/85-05-02).
As a part of the decommissioning of the CX-10 reactor at the Lynchburg
Research Center (LRC) the licensee disposed of the reactor's fuel rods by
transfering them to Department of Energy (00E) facilities at Oak Ridge. The
reactor had not been operated above one kilowatt.
The fuel was
approximately 2.5 percent enriched in U-235 and was considered unirradiated
per the 00T definition in 49 CFR 173.403.
LRC transferred the fuel in
containers covered by NRC Certificate of Compliance No. 9069.
LRC refurbished the containers prior to use.
The first shipment of CX-10
fuel arrived at the Oak Ridge National Laboratory (ORNL) on August 21, 1984.
On arrival ORNL personnel discovered a crack in the outer skin of the
outside container just beneath the horizontal weld on one of the lower
ratchet binders. The crack did not affect package integrity.
The ratchet
binder is one of twelve primary closure devices. There are also twelve high
strength latch pins which serve as secondary closure devices.
After
i
receiving notification of this crack from ORNL, the licensee reviewed
photographs of the loaded packages taken prior to shipment and observed that
the crack was evident prior to shipment.
The licensee, as corrective
_
.
.
_ _ .
-
.
-
.
__


                                                      ._. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _     _ - ___
._. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
  -
_ - ___
-
.-
.-
                                        5
5
  action, fixed the crack and began performing an extensive receipt inspection
action, fixed the crack and began performing an extensive receipt inspection
  each time the containers arrived back on site and prior to each loading of
each time the containers arrived back on site and prior to each loading of
  fuel for shipment. Failure to ensure that the closure device on a package
fuel for shipment. Failure to ensure that the closure device on a package
  of special nuclear material was free of defects prior to shipment was
of special nuclear material was free of defects prior to shipment was
  identified as another example of an apparent violation of 10 CFR 71.87.
identified as another example of an apparent violation of 10 CFR 71.87.
  (50-013/85-01-01).
(50-013/85-01-01).
5. Enforcement Conference
5.
  An enforcement conference was held on June 27, 1985, to discuss recent
Enforcement Conference
  violations concerning the transportation of radioactive material.                         The
An enforcement conference was held on June 27, 1985, to discuss recent
  following persons were in attendance:
violations concerning the transportation of radioactive material.
  (1) Babcock and Wilcox Lynchburg Research Center
The
        T. C. Engelder, Laboratory Director
following persons were in attendance:
        C. E. Bell, Facility Manager
(1) Babcock and Wilcox Lynchburg Research Center
        A. F. Olsen, License Administrator
T. C. Engelder, Laboratory Director
        J. W. Cure, III, Health and Safety Supervisor
C. E. Bell, Facility Manager
  (2) Nuclear Regulatory Commission
A. F. Olsen, License Administrator
        J. P. Stohr, Director, Division of Radiation Safety and Safeguards
J. W. Cure, III, Health and Safety Supervisor
        G. Jenkins, Director, Enforcement and Investigation Coordination
(2) Nuclear Regulatory Commission
        D. Collins, Chief, Emergency Preparedness and Radiological
J. P. Stohr, Director, Division of Radiation Safety and Safeguards
            Protection Branch
G. Jenkins, Director, Enforcement and Investigation Coordination
        C. Hosey, Chief, Facilities Radiation Protection Section
D. Collins, Chief, Emergency Preparedness and Radiological
        E. McAlpine, Chief, Material Control and Accountability Section
Protection Branch
        J. Kahle, Fuel Facilities Project Manager
C. Hosey, Chief, Facilities Radiation Protection Section
        R. Albright, Radiation Specialist
E. McAlpine, Chief, Material Control and Accountability Section
  During the meeting, licensee personnel presented discussions of their
J. Kahle, Fuel Facilities Project Manager
    radioactive material transportation organization, discussions of each
R. Albright, Radiation Specialist
    inspection finding and corrective actions.
During the meeting, licensee personnel presented discussions of their
radioactive material transportation organization, discussions of each
inspection finding and corrective actions.
}}
}}

Latest revision as of 07:09, 12 December 2024

Insp Repts 50-013/85-01 & 70-0824/85-05 on 850610-14. Violation Noted:Failure to Package Low Specific Activity Radioactive Matl in Strong Tight Package & Failure to Label Packages of Radioactive Matl Per Burial Facility License
ML20133P811
Person / Time
Site: Lynchburg Research Center, 07000824
Issue date: 07/18/1985
From: Albright R, Hosey C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20133P738 List:
References
50-013-85-01, 50-13-85-1, 70-0824-85-05, 70-824-85-5, NUDOCS 8508140494
Download: ML20133P811 (5)


See also: IR 05000013/1985001

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Report Nos.:

70-824/85-05, 50-013/85-01

Licensee: Babcock and Wilcox Company

Lynchburg Research Center

Lynchburg, VA 24505

Docket Nos.:

70-824 and 50-013

License No.:

SNM-778 and

CX-10

Facility Name: Lynchburg Research Center

Inspection Conducted: June 10-14, 1985

Inspector:

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y R. H. AlbrigTt

Date signed

Approved by: M

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C. M. Hc'sey, Sect ion Chief

Date Signed

DivisionofRadia(tionSafetyandSafeguards

SUMMARY

Scope: This routine, unannounced inspection entailed 17 inspector-hours on site

in the area of transportation of radioactive material.

Results:

Three violations - Failure to package low specific activity (LSA)

radioactive material in a strong tight package; failure to ensure that the

closure device on a package of Fissile Class II material was free of defects

prior to shipment and failure to ship Fissile Class II material in a tested,

approved package; failure to label packages of radioactive material as required

by the burial facility license.

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REPORT DETAILS

1.

Persons Contacted

Licensee Employees

  • A. E. Wehrmeister, Manager, System Development Laboratory
  • J. P. Doran, Manager, Accounting and Administrative Services
  • G. Hoovier, Manager, Building A Decommissioning Project
  • J. W. Cure, Supervisor, Health and Safety
  • A. Olsen, Senior License Administrator

D. Harris, Health Physics Technician

  • Attended Exit Interview.

2.

Exit Meeting

The inspection scope and findings were summarized on June 14, 1985, with

those persons indicated in paragraph 1 above.

The apparent violation of

10 CFR 71.87 for shipment of a package with a crack under a closure bracket,

violation of 10 CFR 70.42 for transferring special nuclear material to a

land disposal facility without the labels required by receiver's license and

violation of 10 CFR 71.5 for the shipment of a package of LSA radioactive

material which failed to meet the strong tight container requirement were

discussed in detail.

Licensee management acknowledged the violations.

The licensee was notified during a telephone conversation on June 19, 1985,

between J. B. Kahle of this office and A. Olsen of the licensee's staff that

failure to choose a package that was proper for the contents was another

example of a violation of 10 CFR 71.87.

The licensee did not identify as proprietary any of the materials provided

to or reviewed by the inspector during this inspection.

3.

Licensee Action of Previous Enforcement Matters

This subject was not addressed in the inspection.

4.

Transportation of Radioactive Material (86740)

On May 29, 1985, NRC Region II received a copy of a letter dated May 20,

1985, from the State of Washington to the B&W Lynchburg Research Center.

The letter described two violations in shipment No. LRC-23.

The first

violation concerned a hole in a drum of LSA radioactive material in

violation of the strong tight package requirement of 49 CFR 173.425.

The

second violation concerned the failure to meet requirements of the U.S.

Ecology land disposal facility license by affixing the correct number of

labels to each package.

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On May 1,1985, the licensee made shipment No. LRC-23 to the U.S. Ecology

land disposal facility at Richland Washington. While unloading the shipment

of drums on May 6, 1985, disposal site personnel observed a hole in the side

of drum number 4740. The waste manifest described the contents of the drum

as uranium oxides on lab trash and equipment.

The radionuclide content

measured was Uranium-234 at 0.03 mil 11 curies, Uranium-235 at 0.002

millicuries, Uranium-236 at 0.0004 millicuries, and Uranium-238 at 0.01

millicuries. The drum was listed as Fissile Exempt and labeled Radioactive

LSA. The licensee's investigation determined that shifting of a 32 pound

metal object inside the container caused the hole. The inspector discussed,

with the U.S. Ecology health physics (HP) technician who identified the hole

in the drum, the details of the U.S. Ecology receipt of shipment No. LRC-23.

The HP technician stated that the drum with the hole had not been moved from

its shipment position in the trailer before the hole was observed. The hole

was observed after drums in front of this drum were removed while unloading

the shipment. The metal object inside the drum which apparently shifted

during transportation and caused the hole was protruding from the hole when

observed by the HP technician.

It was determined that the hole had been

punched through the wall of the Department of Transportation (DOT)

Specification 17 H drum during transport. Surveys outside the hole did not

indicate leakage of radioactive material from the can.

The amount of

radioactive material inside the can would not have caused a significant

public health and safety problem if it had been released.

10 CFR 71.5(a) requires that licensees who transport licensed material

outside the confines of its place of use or delivers such material to a

carrier for transport comply with the requirements of DOT regulations

contained in 49 CFR Parts 170 through 189. 49 CFR 173.425 requires that LSA

materials be shipped in a DOT specification 7A Type A package or a strong

tight package such that there will be no leakage of the package contents

during normal conditions of transport.

In discussions with licensee

representatives and reviews of shipping papers it was determined that three

licensee personnel observed the drum to be in good condition prior to

transport.

No other drums were damaged.

Failure to ship LSA radioactive

material in a DOT Specification 7A Type A package or a strong tight package

was

identified

as

an

apparent

violation

of

10 CFR 71.5(a).

'

(70-824/85-05-01).

1

10 CFR 20.301 prohibits the disposal of radioactive material except under

'

specified conditions including _ transfer to an authorized recipient as

provided in the regulations in Parts 30, 40, 60, 61, 70 or 72 of this

chapter, whichever is applicable.

10 CFR 70.42 states requirements that

must be met prior to transferring special nuclear material (SNM).

One

requirement is that SNM may be transferred to any person authorized to

receive such SNM under terms of a specific license or a general license or

their equivalents issued by the Commission or an Agreement State.

U.S.

Ecology license, from the State of Washington, WN-1019-2, license condition

27(k), requires that when waste is labeled with a DOT White I, Yellow II or

Yellow III label a waste classification label should appear next to or in

close proximity to each DOT label . The license condition further requires

,

that when White I, Yellow II or Yellow III labels are required two of the

1

+.

,

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specific labels must be displayed on each drum.

Land disposal site

personnel observed that six drums in the LRC-23 shipment displayed two

Yellow II labels.

However, only one waste classification label was affixed

to each of the six drums.

Failure to comply with requirements of the

receiver's license by not affixing the appropriate number of waste

,

classification labels was identified as an apparent violation of 10 CFR

'

i

70.42.

(70-824/85-05-03).

10 CFR 71.87 requires that prior to each shipment of licensed material that

certain requirements be met. These include ensuring that the package is

prope for the contents to be shipped, that the package is in unimpaired

physical condition except for superficial defects such as marks or dents and

that each closure device of the packaging is properly installed and secured

and free of defects.

Six drums marked Fissile Class II in shipment LRC-23 were listed on the

shipping papers as DOT specification 7A Type A packages.

The quantity of

SNM in the six drums ranged from '.7,02 grams (3E-2 milli-curies U-235) to

25.92 grams (SE-2 milli-curies). The inspector reviewed the tests performed

for the 55 gallon drum that was used to meet the DOT specification 7A Type A

requirements. 49 CFR 173.465 specifies the tests that Type A packages must

pass prior to use. Fissile Class II packaging, in addition to other Type A

package tests, requires a free drop from a height of 0.3 meter (1 foot) on

each corner. For cylindrical packagings, the 0.3 meter drop shall be onto

each quarter of each rim.

The test data review indicated that the corner

drop test had not been performed. These drums were part of an exclusive use

shipment in a closed transport vehicle.

These packages were not damaged

during the shipment and no leakage of radioactive material occurred.

Failure to perform the required drop test resulted in use of an improper

package to ship Fissile Class II material. Failure to ship the Fissile

Class II material in a proper package was identified as an apparent

violation of 10 CFR 71.87.

(70-824/85-05-02).

As a part of the decommissioning of the CX-10 reactor at the Lynchburg

Research Center (LRC) the licensee disposed of the reactor's fuel rods by

transfering them to Department of Energy (00E) facilities at Oak Ridge. The

reactor had not been operated above one kilowatt.

The fuel was

approximately 2.5 percent enriched in U-235 and was considered unirradiated

per the 00T definition in 49 CFR 173.403.

LRC transferred the fuel in

containers covered by NRC Certificate of Compliance No. 9069.

LRC refurbished the containers prior to use.

The first shipment of CX-10

fuel arrived at the Oak Ridge National Laboratory (ORNL) on August 21, 1984.

On arrival ORNL personnel discovered a crack in the outer skin of the

outside container just beneath the horizontal weld on one of the lower

ratchet binders. The crack did not affect package integrity.

The ratchet

binder is one of twelve primary closure devices. There are also twelve high

strength latch pins which serve as secondary closure devices.

After

i

receiving notification of this crack from ORNL, the licensee reviewed

photographs of the loaded packages taken prior to shipment and observed that

the crack was evident prior to shipment.

The licensee, as corrective

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action, fixed the crack and began performing an extensive receipt inspection

each time the containers arrived back on site and prior to each loading of

fuel for shipment. Failure to ensure that the closure device on a package

of special nuclear material was free of defects prior to shipment was

identified as another example of an apparent violation of 10 CFR 71.87.

(50-013/85-01-01).

5.

Enforcement Conference

An enforcement conference was held on June 27, 1985, to discuss recent

violations concerning the transportation of radioactive material.

The

following persons were in attendance:

(1) Babcock and Wilcox Lynchburg Research Center

T. C. Engelder, Laboratory Director

C. E. Bell, Facility Manager

A. F. Olsen, License Administrator

J. W. Cure, III, Health and Safety Supervisor

(2) Nuclear Regulatory Commission

J. P. Stohr, Director, Division of Radiation Safety and Safeguards

G. Jenkins, Director, Enforcement and Investigation Coordination

D. Collins, Chief, Emergency Preparedness and Radiological

Protection Branch

C. Hosey, Chief, Facilities Radiation Protection Section

E. McAlpine, Chief, Material Control and Accountability Section

J. Kahle, Fuel Facilities Project Manager

R. Albright, Radiation Specialist

During the meeting, licensee personnel presented discussions of their

radioactive material transportation organization, discussions of each

inspection finding and corrective actions.