ML16341B652
| ML16341B652 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 05/29/1981 |
| From: | Book H, Hamada G, Wenslawski F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML16341B654 | List: |
| References | |
| 50-275-81-09, 50-275-81-9, NUDOCS 8106050514 | |
| Download: ML16341B652 (12) | |
See also: IR 05000275/1981009
Text
U,
S
NUCL~mKR REGULATORY CO MISS ION
OFFIC"
OF INSPECTION AND ENFORCEH" iT
REGION V
Report
No.
50 275
Doc)<et
NQ ~
License
No.
Pacific
Gas
and Electric Company
P. 0.
Box 7442
CPPR-39
Safeguards
Group
San Francisco,
94106
N,,piablo Canyon Unit 1
>> ec<<on at~vila Beach, California
I
i
d ta.
April 27-30,
1981'/
//.
Inspectors:
'
H. ramada,
Ragiation Laboratory Specialist
i/
Approved By:
F.
Mens awski, Chief
Reactor Radiation Protection
Section,'pproved
By:.. W<
A
n
'H.
E. Book; Chief Radiologica
Safety Branc
Date
S gned
D te
S gned
Date Signed
Da
e
S gned
.'ugary:
~
s
J
Ins ection
on A ril 27-30
1981
Re ort Ho. 50-275 81-09)
c a
~
Areas Ins ected:
Routine announced
inspection of capability test measurements
an
associated
aboratory quality control programs.
Capability .test
measurements.-..
were conducted
on secondary
standards 'using the Region
V mobil'e: laboratory.
The inspection involved a total of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> onsite
by one inspector
and one
radiation laboratory technician.
Results:
Ro items of noncompliance
were identified in the areas
inspected
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DETAILS
Persons
Contacted
- J. Boots, Supervisor,
Chemistry and Radiation Protection
- W. Ohara,
Sr. Chemistry and Radiation Protection
Engineer
- R. Thor nberry, Plant Manager
D. Unger,
Engineering Trainee
- Indicates those present at the exit interview.
Measurements
and Intercom arison of Standards
Data
Evaluation of the licensee's
capability to perform radiological effluent
measurements
was originally done
by the
NRC in 1977.
However, in the
intervening years
since that initial test,
a turnover in laboratory
personnel
has occurred
and
a new set of measurement
instrumentation
was purchased
to replace the earlier system.
Because of these
changes
and the long interval since the original evaluation effort,
it was determined that Diablo Canyon should
undergo reevaluation prior
to plant startup.
Four different
NRC calibration standards
were provided to the
Unit
1 laboratory for gamma spectrometric analysis.
These
calibration standards
were fabricated for the
NRC by the Radiological
and Environmental
Sciences
Laboratory
(RESL) of the Department of
Energy for calibration of the
gamma spectrometry
system in the
Region
V Mobile Laboratory.
RESL has
been qualified by the National
Bureau of Standards
(NBS) as
an
NBS traceable
laboratory.
Several of the
PGSE calibration standards
were also measured
by the
NRC using the Region
V Mobile Laboratory measurement
system.
This system consists of a Nuclear Data
(ND) 6600
gamma
spectroscopy
system with associated
ND software.
This system
was calibrated with standards
provided by RESL.
The following results
were obtained for the various intercomparison
measurements.
TABLE I
NRC
FACE 'LOADED CHARCOAL CARTRIDGE STANDARD
NUCLIDE
Sn-113
Cs-137=
Y-88
PGEcE
2.03
X 102
2.86
X 102
5.74
X 102
8.66
X 10
1.57
X 103
4'.14
X 103
2.41
X 10
NRC (RESL)
6 sec
1.09
X 102
1.83
X 102
3.53
X 10
7.12
X 102
1.04
X 103
2.75
X 103
1.64
X 10
RATIO
NRC
RESL
1.85
1. 56
l. 63
1.22
1. 51
1.51
1.46
The agreement
between
PGI'AE and
NRC
(RESL) for the
NRC Charcoal
Cartridge
is, at best, marginal.
PGRE is high by about 59* percent
on the average.
(* - Due to poor counting statistics,
Sr-85 was not included in the
average.)
TABLE 2
PG&E FACE LOADED CHARCOAL CARTRIDGE STANDARD
NUCLIDE
Ce-139
Hg-203
Sn-113
Y-88
PGIlE Reference
Value*
's
847
1279
3288
2108
3209
7122
4670
NRC
~s'sec 1174
505
753
1943
. 1264
1985
4583
2957
Ratio
~PG&E
1. 61
1,68
1.70
1.69
1.67
1.62
1.55
1.58
- Reference date - May 15, 1980
Consistent with the results
obtained for the
NRC Charcoal
Cartridge
Standard
(Table 1),
PGSE is biased
high by about
64 percent
on its
own
charcoal
cartridge standard.
TABLE 3
NRC PARTICULATE FILTER STANDARD
RUCLICE
Sn-113
Y-88
PGSE
~ssec.
76.8
148
277
270
708
'713
1036
NRC
(RESL)
's sec
44. 0
73. 8
142
287
417
1103
657
Ratio
PGSE
NRC
RESL
1.75
2. 01
1.95
0. 94
1. 70
1.55
1.58
The results indicate that
PGKE is high by approximately 76* percent
for particulate filters.
(* - Due to poor counting statistics,
was not included in the average for the ratio.)
-3-
TABLE G
PGE(E PARTICULATE FILTER STANDARD
NUCLIDE
Ce-139
Hg-203
Sn-113
.'Y-88
PGstE
Reference
Value
uCi
1.29
X 10-2
2.51
X 10 2
4.06
X 10
1.02
X 10
8.24
X 10
22
9.50
X 10 I
1.82
X 10
1.18
X 10-1
NRC
uCi
5.11
X 10 3
9.73
X 10 2
1.59
X 10
4.62
X 10 2
4.43
X 10 2
5.38
X 10
1.08
X 10 I
6.98
X 10
Ratio
~PGBE
NRC
2. 52
2.58
2.55
22
1.86
1.77
1. 69
1.69
The
PGSE Particulate Filter Standard is high by about
a factor of
2* over the
NRC results.
(* - Due to poor counting statistics,
Hg-203 was not included in the average for the ratio.)
The larger
bias indicated for the intercomparison
tabulated
in Table 4 (as
compared to Table 3) could be due in part to deterioration of
the
PGSE Particulate Filter Standard.
Visual evidence of some
deterioration of this standard
was observed.
TABLE G
NRC - 10 ML LI UID SCIENTILLATION VIAL STANDARD
NUCLIDE
=
Ce-139
Hg-203
Sn-113
Sr -85
Y-88
PGSIE
~ssec
82
83
96
294
417
529
348
890
431
NRC
P~~ssec
66
59
70
197
214
406
249
679
338
Ratio
~PGBE
NRC
1. 24
1.41
l. 37
1.49
1.95
1.30
l. 40
1.31
1.28
For the scintillation vial geometry,
PGIt.E is biased
high by approximately
42 percent.
~Ee era
145.22
Kev
172. 10 Kev
202.84
Kev
374.96
Kev
TABLE 6
NRC
(NBS) Xe-127
GAS
STANDARD
uCi
66.3
65.7
64.1
63. 4
Reference
Value
uCi
57. 3
57. 3
57.3
57. 3
The licensee's
gas measurement
is in good agreement with the expected
value.
The differences
in the results
as
a function of energy
can
be
attributed to a greater
wall thickness of the
PG&E glass bulb.
TABLE 7
NRC
1
LITER MARINELLI SOLUTION STANDARD
NUCLIDE
Sn-113
Y-88
~ssec. 101
323
583
917
1940
7320
3960
NRC (RESL)
s sec 188
317
608
1225
1783
4733
2817
RATIO
PG&E NRC
RESL
'0.54
1. 02
0. 96
0.75
1.09
1.55
1.41
The results for the
NRC 1-Liter Narinelli Solution Standard
are mixed.
A few nuclides agree,
but others are too high or too low.
Nhile the licensee's
gas calibration appears
to be valid, those
calibrations
performed with the mixed gamma source are biased
high
by 40-80 percent.
The
gamma spectroscopy
system should
be recalibrated
with new standards.
The licensee
has agreed to do this and
has ordered
new standards
from the National
Bureau of Standards
(NBS).
This is an open item which must be resolved prior to initial criticality
of Unit l.
(Item No. 81-09-01).
1
~
-5-
3.
Review of ualit
Control Procedures
The following documents
were reviewed for adequacy of quality control
(gC) programs for sampling
and measurements.
a.
"Chemical Analysis Procedures
- Liquid Radwaste
Discharge
Nanagement"
No.
CAP A-5 Revision l.
b.
"Laboratory Instrumentation Calibration Schedule"
No.
CAP A-4.
c.
System
45 - Training Nanual.
d.
ND-66 - Training Nanual.
e.
APT Manual
f.
Plant Nanual:
(1)
Chemical
and Radiochemical
Procedures
Volume 8.
(2)
Administrative Procedures
Volume 1.
The documents
reviewed were found to be generally adequate with respect
to gC procedures.
PG&E also
has provisions for an internal audit program
through its quality control section.
4.
Exit Interview
Inspection findings were discussed
with PG&E personnel
referenced
in Paragraph
1.
PG&E management
was informed of the disagreement
between
PG&E and
NRC on measurements
performed
on various non-gaseous
calibration standards.
PG&E agreed to recalibr ate its gaFm spectroscopy
system with new standards,
and to do this prior to initial criticality
of Unit 1.
PG&E management
was also informed that the
NRC, through
RESL,
would be sending the Unit
1 laboratory, spiked s'olutions containing
Sr-89, Sr-90, H-3, and possible
mixed beta emitters; for gross
beta
analysis,
as
a further check on the anaiysis of these radionuclides.
(Item No. 81-09-02)
Finally,
PG&E Nanagement
was apprised of our intention
to perform a similar inspection with the Region
V Nobile Laboratory
after the recalibrations
had
been completed.
t