ML17285A154
| ML17285A154 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 12/27/1988 |
| From: | Holahan G Office of Nuclear Reactor Regulation |
| To: | Scarano R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| TAC-69278, NUDOCS 8901030141 | |
| Download: ML17285A154 (7) | |
See also: IR 05000397/1988026
Text
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UNITEDSTATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON, D. C. 20555
December 27, l988
MEMORANDUM TO:
FROM:
SUBJECT:
Ross
A. Scarano,
Director
Division of Radiation Safety
8 Safeguards,
RV
Gary M. Holahan, Acting Director
Division of Reactor Projects - III,
IV, V and Special Projects
Office of Nuclear Reactor Regulation
NRR ASSISTANCE
TO REGION
V ON WNP-2 DRYWELL SAMPLE
By letter dated August 26,
1988 you provided us with a copy of inspection
report 50-397/88-26
in which you reported your determination that the licensee
is not analyzing
containment
vent and
pur ge releases
for radioactivity.
The
inspection report describes
the licensee's
interpretation of the technical
specifications.
You asked
us to review the record
and answer
two specific
questions:
l.
"In view of the licensee's
interpretation
as found and described
in the enclosed
report,
does Technical Specification 4.11.2.1
and
Table 4.1-2 require
a sample of drywell atmosphere
be taken
and
analysed prior to each vent and purge operation
through the
system?"
2.
"If prior-to-release
samples
are required,
should this be reflected
in the
ODCM, along with the appropriate
Decontamination
Factor to
account for SGT cleanup?"
We have reviewed the material which you provided.
The answer to the first
question is "yes."
WNP-2 Technical Specification 4.11.2.1.2 with its
Table,4.11-2
requires that
a grab
sample
be taken prior to each
PURGE and
VENT
from primary containment.
Technical Specification 4.11.2.8.3
provides additional
drywell sampling requirements for the case of purging or venting through other
than the standby
gas treatment
system
(SGTS).
These additional
samples
would
not be required
when purging or venting through the
SGTS.
With regard to the second question,
Technical Specification 4. 11.2.1.2 states:
"The dose rate
due to iodine-131,
iodine-133, tritium, and all radionuclides
in particulate
form with half lives greater
than
8 days in gaseous
effluents
shall
be determined to be within the above limits in accordance
with the
A
890i030i4i Sai227
ADOCK 05000397
9
Ross
A. Scarano
December
27, l988
methodology
and parameters
in the
ODCH by obtaining representative
samples
and
performing analyses
in accordance
with the sampling
and analysis
program
specified in Table 4.11-2."
This most certainly ties the sampling
and analysis
requirements
to dose rate determinations
in accordance
with the
ODCH.
Thus
statements
regarding
the use of the prior-to-release
samples
in making these
determinations
should be incorporated
in the
ODCH.
Sincerely,
/s/
Gary H. Molahan, Acting Director
Division of Reactor Projects - III,
IV., V and Special
Projects
Office of Nuclear Reactor Regulati'on
DISTRIBUTION .,
NRC
8 Local
PD5 Reading
GHMo 1 aha n
HVirgi1io
GKnighton
JLee
F. Congel
D. Kirsch
J.
Lynch
K. Desai
RSamworth
OGC (f/info only)
EJordan
BGrimes
ACRS (10)
LJCunningham
W. Wayne Heinke
CONTACT:
Robert B. Samworth,
X21364
(SCARANO.HEHO)
- See previous concurrence
DRSP/PD5
DRSP/D:PD5
RBSamworth:dr* GWKnighton*
/
/88
/
/88
OFFICIAL RECORD
COPY
(A)AD:DRSPQD/
HJVirgilio
lg/5'/88
GHMolahan
/lg/88
0
II,I
C'I
ll
r
"l
-2-
Nemo to Ross
Scarano
methodology
and parameters
in the
ODCtf by obtaining representative
samples
and
performi'ng analyses
in accordance
with the sampling
and analysis
program
specified~jn Table 4.11-2."
This most certainly ties the sampling
and analysis
requirements<to
dose rate determinations
in accordance
with the
ODCN.
Thus
statements
regarding the use of the prior-to-release
samples
in making these
determinations~should
be incorporated
in the
ODCtl.
Sincerely,
cc:
See next page
DISTRIBUTION
NRC 5 Local
PD5 Reading
Gt1Ho1 ahan
tlVirgi1 io
GKnighton
JLee
Gary H. Holahan, Acting Director
';Division of Reactor Projects - III,
IV, V and Special Projects
Office of Nuclear Reactor Regulation
RSamworth
OGC (f/info only)
EJordan
BGrimes
ACRS (10)
LJCunningham
W. Wayne tleinke
CONTACT:
Robert
B. Samworth,
X21364
Q(S~A
A 0 CENO)
DRSP/PD5
DRSP/D:PD5
RBSamworth:dr
GWKnighton
i'~ /%/88
(( /p~/88
OFFICIAL RECORD
COPY
(A)AD:DRSP35
MJVirgilio
/
/88
(A)D:DRSP
GNHolahan
/
/88
~
~
t
~t
k
Ross
A. Scarano
December
27,
1988
methodology
and parameters
in the
ODCt) by obtaining representative
samples
and
performing analyses
in accordance
with the sampling
and analysis
program
specified in Table 4.11-2."
This most certainly ties the sampling
and analysis
requirements
to dose rate determinations
in accordance
with the
ODCN.
Thus
statements
regarding the use of the prior-to-release
samples
in making these
determinations
should be incorporated
in the
ODCN.
Sincerely,
Gary N.
Ho 1 ah an, Acting 0irector
Division of Reactor Projects - III,
IV, V and Special
Projects
Office of Nuclear Reactor Regulation
CONTACT:
Robert
B. Samworth,
X21364
4
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4
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