ML17053D004
| ML17053D004 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/18/1981 |
| From: | Clemons P, Knapp P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17053D002 | List: |
| References | |
| 50-220-81-25, NUDOCS 8201250052 | |
| Download: ML17053D004 (6) | |
See also: IR 05000220/1981025
Text
U.
S.
NUCLEAR REGULATORY COMMISSION
OFFICE
OF INSPECTION AND ENFORCEMENT
Region I
Report
No. 50-220/81-25
Docket No. 50-220
License
No.
Priority
Category
C
Licensee:
Nia ara
Mohawk Power Cor oration
300 Erie Boulevard West
S racuse
13202
Facility Name:
Nine Mile Point
1
Inspection At:
Barnwell
Report,
epared
By:
P.
Clemons
adia ion Specialist
Approved By:
P.
.
pp,
C
>e
,
acili
diation
Protection Section,
Technic
1 Inspection
Branch
da
e
ig ed
n.-LF V'f
date
signed
Ins ection
Summar
Ins ection
on
Se tember 23,
1981
b
a re resentative
of the
De artment of Environmental
Control
Niagara
Mohawk Power Corporation
was the originator of a waste
shipment which
was inspected
at the Chem-Nuclear
Systems,
Inc. burial site.
Results:
One apparent
item of noncompliance
was identified (the transfer
of byproduct material
in a form the recipient
was not authorized to receive).
820i250052 820i07
ADOCK 05000220
9
,
r
1
1
DETAILS
On September
21,
1981,
the Niagara
Mohawk Power Corporation dispatched
a
shipment of licensed material
consi sting of 7.458 curies of solidified
evaporator
bottoms
as
LSA radioactive
waste to the Chem-Nuclear
Systems,
Inc. burial site at Barnwell, South Carolina.
The shipment
was
made in
a
'hem-Nuclear
shipping cask,
Model
No.
14-195-H.
On September
23,
1981,
a representative
of the South'arolina
Department of
Health
and Environmental
Control inspected
the shipment.
The inspection
consisted
of a review of shipping papers,
placarding,
marking and labeling,
radiation measurements,
observations
by the representative,
and examination
of the packages
and the tractor-trailer.
A copy of the report, without attachments,
prepared
by the representative
is attached.
The report states that the inner liner of the cask,
containing
the solidified evaporator
bottoms,
was punctured
by drilling several
holes
through the wall of the liner, and
170 gallons of liquid were drained out
of the liner.
Urea formaldehyde
was
used
as the solidification media.
Condition
No.
27 of the Chem-Nuclear
Systems,
Inc. Agreement State
License,
License
No. 097, states:
"The licensee
may receive
aqueous
liquids solidified with one of'he
following solidification media provided the requirements
of other
conditions
as specified in this license
are met:
(a)
Dow media
(b)
Cement
(c)
Urea
Formaldehyde
(d)
Asphalt
(e)
Custom Media
(f) Solidification media
and processes
reviewed
and approved
by the
U.S.N.R.C. Office of Nuclear Reactor Regulations,
subject to
final approval
by the S.C.
Department of Health and Environmental
Control,
Bureau of Radiological Health."
Condition
No.
26 of License
No.
097 states
that solidified radioactive
was'te shall
have
no detectable
free standing liquid.
License
No.
097
defines
"no detectable
free standing liquid" as follows:
"(a) One percent
(1%) liquid by waste
volume until December
31,
1980.
(b)
Effective January
1,
1981, one-half percent
(0.5%) by waste
volume or one gallon of non-corrosive liquids per container,
whichever is less.
I j
In lieu of the requirements
of sub-paragraph
(b) above, solidified
waste containing liquids in excess of one-half percent
(0.5%) by waste
volume, but less
than
one percent
(1%) liquid by waste
volume,
may be
received
and disposed of in approved
high integrity containers."
In an October
15,
1981,
telephone
conversation with P.
Clemons of the
Region I office,
a state of South Carolina representative
reported that the
inner liner used in this shipment
had been designated
as
a high integrity
container
by the state
and that the 1.0 percent limit is applicable.
The
170 gallons of liquid radioactive waste drained
from the liner corresponds
to 11.7 percent of the waste
volume.
10 CFR 30.41 prohibits transfer of byproduct material
unless it is in-a
form authorized
by the recipient's
NRC or Agreement State license.
As
noted
above,
South Carolina License
No.
097
prohibits the receipt of
solidified waste with "detectable
free standing liquid,'"which is defined in
this case
as liquid in excess
of 1.0 percent
by waste 'volume for high
integrity containers.
This represents
noncompliance with 10 CFR 30. 41"(81-25-01).
The Nine Mile Point Station Superintendent
was informed of this apparent
item of noncompliance with NRC requirements
in a telephone
conversation
with P.
Clemons
on October 7,
1981.
V