ML17328A449
| ML17328A449 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/20/1990 |
| From: | Holtzman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17328A450 | List: |
| References | |
| 50-315-90-19, 50-316-90-19, NUDOCS 9009260101 | |
| Download: ML17328A449 (20) | |
See also: IR 05000315/1990019
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION III
Report Nos.
50-315/90019(DRSS);
50-316/90019(DRSS)
Docket Nos. 50-315;
50-316
Licensee:
Company
1 Riverside
Plaza
Columbus,
OH
43216
License
Nos.
Facility Name:
D.
C.
Cook Nuclear Plant, Units
1 and
2
Inspection At:
D. C.
Cook Site,
Bridgman, Michigan
Inspection
Conducted:
August 27-31,
1990 (On-site)
September
10-14,
1990 (Telephone
discussions)
~//sss
~~wsc
Inspector:
R. B. Holtzman
Date
u3
Accompanying Inspector:
A. G.
J nuska
Date
Approved By:
M. C. Schumacher,
Chief
Radiological Controls
and
Chemistry Section
Date
Ins ection
Summar
Ins ection
on Au ust 27-31,
1990,
and
Se tember 10-14,
1990 (Tele hone
discussions
Re ort Nos.
50-315/90019
DRSS;
50-316
9
19
DRSS
reas
Ins ected:
Routine unannounced
inspection of the radiochemistry
program
inc uding
1
review of an open item (IP 92701);
(2) implementation of the
counting
room quality assurance/quality
control
programs
(IP 84750);
and (3)
comparison of measurements
of split radiological
samples with the Mobile
Labo'ratory'(IP 84750
and IP 84725).
Results:
Results of the radiological confirmatory measurement
program were
Vair w>th weakness
in
gamma specrtrometry
performance
owing mainly to poor
analytical sensitivity.
The laboratory quality assurance
was otherwise
satisfactory.
The licensee's
inter laboratory crosscheck
results with vendor
laboratories
were very good.
No violations or deviations
were identified.
oioi 900520
9
ADOCK 0=0003i
DETAILS
Persons
Contacted
,~A.
A. Blind, Plant Manager,
D.C.
Cook (DCC)
~J.
R.
Rutkowski, RPM-Technical,
DCC
,~J, Wojcik, TPS/Superintendent,
DCC
~L. Umphrey, TPS/Administrative
Compliance Coordinator,
DCC
K. Haglund,
TPS/ General
Chemical Supervisor,
DCC
',~R.
Looker, TPS/Chemical
Supervisor,
DCC
,zD.
Loope, TPS/Plant Radiation Protection Supervisor,
DCC
D. Bublick, TPS/Senior
Chemical Technician,
DCC
~D. Williams, TPS/Radiation
Protection Supervisor,
DCC
~T. Andert, TPS/Sr.
Chemical Specialist,
DCC
~J.
Kambach,
TPS/Radiation Protection,
DCC
~D. Noble, TPS/Health Physicist,
DCC
'S.
Lehrer, TPS/Radiation
Protection Supervisor,
DCC
~J.
H.
Long, TPS/Radwaste
Handling Supervisor,
DCC
~B.
A. Jepkema,
Site gA,
AEPSC
~J.J.
Nadeau,
Site gA,
AEPSC
~S. Clovis,
Rad Support,
AEPSC
~J.
Isom, Senior Resident Inspector,
NRC
The inspectors
also interviewed other licensee
personnel
in various
departments
in the course of the inspection.
~Present at the Exit Meeting on August 31,
1990.
zTelephone
discussions
held during the period September
10-14,
1990.
2.
Licensee Action on Previous
Ins ection Findin s
(Cl osed)
Open Item (50-315/90012-01; 50-316/90012-01):
The licensee
analyzed
a split liquid radwaste
sample for gross beta,
gross alpha,
Sr-89 and Sr-90
and submitted the results to the Region III
Office for comparison with the results with the portion submitted to the
NRC Reference
Laboratory,
The Radiological
and Environmental
Sciences
Laboratory
(RESL) in Idaho.
The, comparisons
of the results
are
presented
in Table
1 with the comparison criteria in Attachment 1.
The licensee
had five agreements
in six analyses
plus
one noncomparison
due to low resolution.
3.
Confirmator
Measurements
IP 84750
a.
Radiological Split Sample
The licensee split a liquid radwaste
sample with the
NRC to be
analyzed for gross beta,
gross alpha,
Sr-89 and Sr-90 by
the license
and the results
reported to Region III for comparison
with those of RESL.
This will be followed under
Open Item Nos.
(50-315/90019-01;
50-316/90019-01).
0
0
b. Confirmatory Measurements
Results
Samples of primary reactor coolant
(RCS),
RCS filters (crud
filters), liquid radwaste,
offgas samples,
and spiked charcoal
cartridges
and air particulate filters were analyzed for gamma
emitting isotopes
by the licensee
on several
detectors,
and in,the
Region III Mobile Laboratory
on site.
Comparisons of the results
are presented
in Table
2 with the comparison criteria in Attachment
1.
The licensee
achieved
63 agreements
in 85 comparisons.
Four of
the disagreements
were nuclides quantized
by both the licensee
and
the
NRC.
These
were Cs-134 in two primary coolant
(RCS) samples,
and Xe-133
and Xe-135 in the offgas
(condenser air ejector)
sample.
The licensee
is working on the resolution of the discrepancies.
The remaining
18 disagreements
were nuclides identified by the
NRC
system,
but not by the licensee's
owing to the low sensitivity of
the licensee's
current analysis
system which had particular
difficulty in resolving
peaks
on the
RCS crud filters.
The problems
appeared
to stem from both hardware
and software deficiencies.
It
was noted that the detector resolutions
were poor with full width
half maximum
(FWHM) values for Co-60 (1332-keV peak) of about
3
keV, compared to that in the newer licensee
system of about 1.8 keV.
The
new system
was purchased
as
a replacement for the older one
and
the licensee
was in the process
of developing operating,
gA, and
operator training procedures
required to make the system operational.
The results
from a crud filter and
a primary coolant
sample
analyzed
by the licensee
on the
new system were in full agreement
with those
of the
NRC.
Licensee
representatives
agreed
to have the
new system operational
'by the end of October
1990 and, in the
mean time, assure
that the
analyses
made
on the older system
meet applicable sensitivity
requirements
by taking such measures
as increasing
counting times
or sample size.
This matter will be reviewed in subsequent
inspections
under
Open Item Nos.
(315/90019-02;
316/90019-02).
No violations or deviations
were identified.
4.
ual it
Assurance
ua1 it
Control
A
C
The inspectors
reviewed the laboratory radioactivity measurements
gA/gC program, including physical facilities and laboratory operations.
Housekeeping
was generally good.
The chemistry laboratories
were
recently ref'urbished
and the cold laboratory
was brought into the
radiological controlled area.
The counting
room was very small, but
it appeared
to have adequate
equipment
and the necessary
workspace.
Replacement
of the old gamma spectrometer
system with the
new should
make more
room available in this room.
The liquid scintillation
counter is being upgraded with a
new Beckman
Chemical Technolgists
(CT) observed
during sample acquisition
and
preparation
appeared
to have
good laboratory technique
and
be
knowlegeable
about the counting systems.
The inspectors
reviewed selected
radiochemistry control charts for the
past year.
The charts,
based
on results
from a Cs-137 source
check,
had + two and three standard
deviation
(SD) warning and control limits,
repectively.
These limits were derived from a Chi-squared calculation
made from 21 measurements
done at the start of of the year, or as
needed
during the year.
In addition,
a calibration standard
was counted daily,
and the results of the Cd-109,
and Co-60 peaks
were each plotted
and the efficiencies,
FWHM, and activities were tabulated.
The
inspectors
noted that for some of the
Ge detectors,
the control limits
were
somewhat greater
then warranted
by the data.
Possibly the control
parameters
would better reflect instrumental
performance if determined
more frequently,
from recent
check source
data,
rather than from a
few'hort-term
data points taken in the past.
A licensee
representative
noted that this would be considered.
The radiological interlaboratory
comparison
program results with a
vendor (Analytics, Inc.) for the last four quarters
were very good
with no apparent
bias from the vendor's results;
only one comparison
in over 150 was in disagreement.
Overall, the gA/gC program appears
to be operating satifactorily.
No violations of deviations
were identified
Audits and
A
raisals
The inspectors
reviewed the most recent corporate
assessments
of the
Radiochemical
program, guality Assurance
Audit No. gA-89-24, Chemical/
Radiochemical
Control
Program
(PNI-6020) conducted
September
8, to
November 10,
1989.
This includes
a detailed review of the counting
laboratory gA/gC program.
The audit appeared
to be adequate
and the
auditors
knowlegeable.
Some, deviations
were noted
and corrected in a
timely manner,
usually during the audit period.
No violations or deviations
were identified.
~0en Items
Open items are matters
which have
been discussed
with the licensee,
which will be reviewed further by the inspectors,
and which involve some
action
on the part of the
NRC or licensee,
or both.
Two open items were
disclosed in Section
3.
Exit Interview
The scope
and findings of the inspection
were reviewed with licensee
representatives
(Section 1) at the conclusion of the inspection
on
August 31,
1990.
The inspectors
discussed
the preliminary confirmatory
measurements
results.
Licensee representatives
agreed to make the
new
gamma spectrometry
system operational within 60 days
and to try to
improve the sensitivity of the present
system in the interim.
Additional discussions
were held with licensee
representatives
during
the period September
10-14,
1990, with a supplemental
exit interview on
September
14,
1990.
'I
III
During the exit interview, the inspectors
discussed
the likely
informational content of the inspection report with regard to-documents
or processes
reviewed by the inspectors
during the inspection.
Licensee
representatives
did not identify any such
documents
or processes
as
proprietary.
Attachments:
1.
Table 1, Radiological Interlaboratory
Split Sample Results,
2nd quarter
1990
2.
Table 2, Radiological Interlaboratory
Comparison
Results,
3rd quarter
1990
3.
Attachment 1, Criteria for Comparing
Radiological
Measurements
TABLE 1
U.S.
NUCLEAR REGULATORY COMMISSION
REGION III
CONFIRMATORY MEASUREMENTS PROGRAM
FACILITY D.C.
COOK
FOR THE 2nd QUARTER OF 1990
Radwaste Split Sample,
6/6/90
SAMPLE
NUCLIDE
NRC VAL. NRC ERR.
LIC.VAL.
LIC.ERR.
RATIO
RESOL.
RESULT
RAINASTE GROSS
A 1.10E-08
SPLIT
GROSS
B 4.60E-04
1.30E-01
9.30E-05
SR-89
5.30E-07
1.60E-07
TEST RESUITS:
A=AGREEMENT
D=DISAGREEMENT
- =CRITERIA RELAXED
N=NO COMPARISON
5.00E-09
2.00E-05
2.00E-03
2.00E-06
4.00E-08
2.00E-08
<3.20E-08
6.05E-04
1.19E-01
1 '9K-04
4 '3E-07
1.11E-07
6.06E-05
2.60E-04
1.09E-05
4.73E-08
1.10E-08
2 ~ 91
1.32
0.92
1.17
0.89
0.69
2.2
N
23.0
A
65.0
A
46.5
A
13.3
A
8.0
,
A
19-Sep-90
TABLE 2
U S.
NUCLEAR REGULATORY COMMISSION
REGION III
CONFIRMATORY MEASUREMENTS PROGRAM
FACILITY D.C.
COOK
FOR THE 3RD QUARTER OF 1990
SAMPLE
NUCLIDE
NRC VAL. NRC ERR.
LIC.VAL.
LIC.ERR.
RATIO
RESOL.
RESULT
CHARCOAL I-131
1.75E-01
8.19E-04
SPIKE
DET 3
1.95E-01
2.76E-02
1.11
213.7
A
CHARCOAL I-131
1.75E-01
8.19E-04
2.05E-01
SPIKE
DET,4
2.90E-02
1.17
213.7
A
WASTE
LIQUID
DET 1
LIQUID
WASTE
DET 3
PRIMARY
COOLANT
DET 3
CO-58
SB-125
CS-134
CO-58
SB-125
CS-134
NA-24
RB-88
Y-88
CS-134
CS-138
I-132
I-133
I-134
I-135
3.82E-06
9.07E-05
1.13E-05
6.20E-06
7.88E-05
7.53E-05
3.82E-06
9.07E-05
1.13E-05
6.20E-06
7.88E-05
7.53E-05
5.00E-03
7.61E-02
2.32E-04
2.74E-04
2.66E-04
8.62E-03
2.58E-03
1.51E-03
5.04E-03
2.93E-03
2.06E-07
5.91E-07
2.75E-07
6.80E-07
6.38E-07
5.31E-07
2.06E-07
5.91E-07
2.75E-07
6.80E-07
6.38E-07
5.31E-07
7.13E-05
1.11E-02
3.37E-05
2.48E-05
3.21E-05
4.48E-04
7.45E-05
3.67E-05
1.81E-04
1.77E-04
4.16E-06
1.09E-04
1.35E-05
O.OOE+00
9 '1E-05
9.00E-05
4.44E-06
1.11E-04
1.36E-05
7.88E-06
8.20E-05
9.18E-05
4 '8E-03
9.42E-02
2.44E-04
1.14E-04
1.80E-04
O.OOE+00
2.25E-03
1 '9E-03
4.52E-03
2.45E-03
3 15E-07
2.57E-06
4.80E-07
O.OOE+00
1.18E-06
1.41E-06
1.98E-07
9.31E-07
3.42E-07
7.26E-07
1.29E-06
9.75E-07
1.04E-04
1.26E-02
3.60E-05
3.08E-05
3.62E-05
O.OOE+00
1.25E-04
6.36E-05
2.10E-04
1.76E-04
1.09
18.6
1.20
153.5
1.19
41.1
9.1
1 ~ 16
123.5
1.20
141.8
1.16
18 '
1.22
153.5
1.20
41.1
1.27
9.1
1.04
123.5
1 22
141.8
0.86
70 F 1
1.24
6.9
1.05
F 9
0.42
11.0
0.68
8.3
19.2
0.87
34.6
0.92
41.1
0.90
27.8
0.84
16.6
A
A
A
D
A
A
A
A
A
A
A
A
A
A
A
D
A
D
A
A
A
A
Page
1
19-Sep-90
0
SAMPLE
NUCLIDE
NRC VAL. NRC ERR.
LIC.VAL.
LIC.ERR.
RATIO
RESOL.
RESULT
PRIMARY
COOLANT
DET 4
NA-24
RB-88
Y-88
CS-134
CS-138
I-132
I-133
I-134
I-135
5.00E-03
7.61E-02
2.32E-04
2 '4K-04
2.66E-04
8.62E-03
2.58E-03
1 ~ 51E-03
5.04E-03
2.93E-03
7.13E-05
1 ~ 11E-02
3.37E-05
2.48E-05
3.21E-05
4.48E-04
7.45E-05
3.67E-05
1.81E-04
1 ~ 77E-04
4.46E-03
1.05E-01
1.97E-04
8.45E-05
1.70E-04
O.OOE+00
2.26E-03
1.29E-03
4.45E-03
2.37E-03
1.02E-04
1.26E-02
3.74E-05
3.25E-05
3.17E-05
O.OOE+00
1.21E-04
6.90E-05
2.19E-04
1 '4K-04
0.89
1.38
0.85
0.31
0.64
0.88
0.85
0.88
0.81
70 '
6 ~ 9
6.9
11.0
8.3
19.2
34.6
41.1
27 '
16.6
A
A
A
D
A
D
A
A
A
A
PRIMARY
COOLANT
CRUD
NA-24
CR-51
PRIMARY
COOLANT
CRUD
NA-24
CR-51
FILTR 01 CO-58
DET 4
ZR-97
RH-105
BA-140
I-133
FILTR 41 CO-58
DET. 3
RH-105
BA-140
I-133
1.59E-05
1.59E-05
1.48E-06
6.48E-05
1.59E-06
8.86E-06
1 ~ 05K-06
4.44E-06
2.75E-06
1 ~ 59E-05
1.59E-05
1.48E-06
6.48E-05
1.59E-06
2 '7E-06
8.86E-06
1.05E-06
4.44E-06
2.75E-06
7 '2E-07
2.70E-06
2.70E-07
9.52E-07
3.42E-07
1.51E-06
2.30E-07
9 '9E-07
4.10E-07
7 '2E-07
2.70E-06
2 70E-07
9.52E-07
3.42E-07
4.11E-07
1.51E-06
2.30E-07
9 '9E-07
4.10E-07
1.94E-05
0 'OE+00
O.OOE+00
6.96E-05
O.OOE+00
O.OOE+00
O.OOE+00
O.OOE+00
O.OOE+00
1.67E-05
O.OOE+00
O.OOE+00
6.61E-05
O.OOE+00
O.OOE+00
0 OOE+00
1.40E-06
O.OOE+00
3.42E-06
OBOE-06
O.OOE+00
O.OOE+00
2.54E-06
0 ~ OOE+00
O.OOEw00
O.OOE+00
O.OOE+00
O.OOE+00
1.56E-06
O.OOE+00
O.OOE+00
2.32E-06
O.OOE+00
O.OOE+00
O.OOE+00
4.98E-07
O.OOE+00
8.27E-07
1.22
1.07
1.05
1.02
1.33
1.24
20.9
5.9
5.5,
68. 1
4.6
5.9
4.6
4
6.7
20.9
5.9
5.5
68.1
4.6
5.3
5.9
4.6
4.4
6.7
A
D
D
A
D
D
D
A
'D
A
AIR PART CO-57
SPIKE
DET.1
ZN-65
6.14E-02
5.68E-02
9.11E-02
1.52E-04
6.00E-02
1.23E-03
2.82E-04
5.76E-02
1.16E-03
6.34E-04,
9.26E-02
2.34E-03
0.98
1.01
1'2
403.9
201.4
.
143.7
AIR PART. CO-57
SPIKE
DET. 3
'ZN-65
6.14E-02
5.68E-02
9.11E-02
1 '2K-04
6 04E-02
2.82E-04
6.23E-02
6.34E-04
9.26E-02
2.33E-04
4.08E-04
8.99E-04
0 98
1. 10
1. 02
403.9
201.4
143.7
GDT 6
DET 4
OFF
GAS
DET 2
AR-41
XE-135
7.07E-04
2.31E-06
1.58E-06
7.65E-07
2.01E-03
XE-131M 6.69E-05
1 ~ 39E-04
0 ~ OOE+00
O.OOE+00
1.41E-05
O.OOE+00
0 'OE+00
2.31E-05
7.23E-04
2 '4E-05
5.26E-07
2.21E-06
2.00E-07
2.32E-07
5.62E-07
4.49E-OB
1.41E-07
2.74E-07
2.01E-OB
1.02
0.96
0.36
0.36
14.5
4.7
30. 6
4.4
6.8
5.4
Page
2
19-Sep-90
SAMPLE
NUCLIDE
NRC VAL. NRC ERR.
LIC.VAL.
LIC.ERR.
RATIO
RESOL.
RESULT
PRIMARY
COOLANT
DET 5
NEW SYS
PRIMARY
COOLANT
CRUD ¹1
FILTER
DET 5
NEW SYS
NA-24
RB-88
Y-88
CS-134
CS-138
I-132
I-133
I-134
I-135
NA-24
CR-51
CO-58
ZR-97
BA-139
I-133
5.00E-03
7.61E-02
2 '2E-04
2.74E-04
2.66E-04
8.62E-03
2.06E-04
2.58E-03
1.51E-03
5 '4E-03
2.93E-03
1.59E-05
1.59E-05
1.48E-06
1.59E-06
6.48E-05
2.17E-06
1.05E-06
2.90E-04
2.75E-06
7.13E-05
1.11E-02
3.37E-05
2.48E-05
3.21E-05
4 '8K-04
4.78E-05
7.45E-05
3.67E-05
1.81E-04
1.77E-04
7.62E-07
2.70E-06
2.70E-07
3.42E-07
9.52E-07
4.11E-07
2.30E-07
8.2BE-06
4.10E-07
4.34E-03
9.42E-02
1.48E-04
2.35E-04
2.04E-04
8.41E-03
1.38E-04
2.54E-03
1.30E-03
4.82E-03
2 '2K-03
1.82E-05
1.77E-05
1 '3E-06
1.73E-06
6.92E-05
2.22E-06
1.55E-06
2.56E-04
3.28E-06
6.60E-05
1.26E-'02
2.75E-05
1.92E-05
2 '3E-05
8.17E-04
3.55E-05
5.90E-05
2 '0E-05
2.78E-04
1.34E-04
8 '0E-07
4.30E-06
4.20E-07
3.05E-07
1.19E-06
4 '3K-07
3.69E-07
4.70E-06
4.57E-06
0.87
1.24
0'4
0'6
0.77
0'8
0.67
'0.98
0'6
0.96
0.79
1.14
1.11
0.76
1.09
1 07
1.02
1'8
0.88
1.19
70.1
A
6.9
A
6.9
A
11.0
A
8 '
A
19.2
A
4 '
A
34.6
A
41.1
A
27.8
A
16.6
A
20.9
'
5.9
A
5.5
A
4.6
A
68.1
A
5;3
A
4.6
A
35.0
A
6.7
A
TEST RESULTS:
A=AGREEMENT
D=DISAGREEMENT
~=CRITERIA RELAXED
N=NO COMPARISON
Page
3
19-Sep-90
ATTACHMENT 1
CRITERIA FOR COMPARING ANALYTICALMEASUREMENTS
This attachment
provides criteria for comparing results of capability tests
and verification measurements.
The criteria are
based
on an empirical
relationship which combines prior experience
and the accuracy
needs of this
program.
In these criteria, the judgment limits are variable in relation to the
comparison of the
NRC's value to its associated
one sigma uncertainty.
As that ratio, referred to in this program
as "Resolution", increases,
the acceptability of a licensee's
measurement
should
be more selective.
Conversely,
poorer agreement
should
be considered
acceptable
as the
resolution decreases.
The values in the ratio criteria may be rounded
to fewer significant figures reported
by the
NRC Reference
Laboratory,
unless
such rounding will result in a narrowed category of acceptance.
RESOLUTION
<4
4 -
7
8-
15
RATIO = LICENSEE VALUE/NRC REFERENCE
VALUE
~Areement
NO COMPARISON
0.5
- 2.0
0.6
- 1.66,
16 -
50
51 - 200
200
0.75 - 1.33
0.80 - 1.25
0.85 - 1.18
Some discrepancies
may result from the use of different equipment,
techniques,
and for some specific-nuclides.
These
may be factored into the acceptance
criteria and identified on the data sheet.
r
P