ML17258A221
| ML17258A221 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/03/1981 |
| From: | Bores R, Jang J, Kottan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17258A219 | List: |
| References | |
| 50-244-81-06, 50-244-81-6, NUDOCS 8110090217 | |
| Download: ML17258A221 (10) | |
See also: IR 05000244/1981006
Text
U.S.
NUCLEAR REGULATORY COMMISSION
OFFICE
OF INSPECTION AND ENFORCEMENT
Region I
Report
No. 50-244/81-06
Docket No. 50-244
License
No.
Priority
Category
C
Licensee:
Rochester
Gas
& Electric
Com an
89 East Avenue
Rochester
14649
Facility Name:
Ginna Nuclear Station
Inspection At:
Ontario,
Inspection
Conducted:
March 16-19,
1981
Inspectors:
J.J.
Kottan, Radiation
Laboratory Specialist
. Jang,
Ra
ation Specialist
9/
date
signed
date
signed
Approved By:
.J.
hief,
Indepgnd
d Environmental
Protedtio
R
ent Measurements
an
n Section,
EPPS
Branch
date
signed
'P
d te signed
Ins ection
Summar
Ins ection
on March 16-19
1981
Re ort No. 50-244/81-06
Areas Ins ected:
Routine,
unannounced
inspection of the licensee's
chemical
and radiochemical
measurements
program using
NRC: I Mobile Radiological
Measure-
ments Laboratory and laboratory assistance
provided by
DOE Radiological
and
Environmental
Services
Laboratory.
Areas reviewed included:
program for
quality control of analytical
measurements,
audit results,
performance
on
radiological
analyses
of split actual effluent samples',
and procedures.
The inspection
involved 48 inspector-hours
onsite
by 2
NRC regional
based
inspectors.
Results:
Of the four areas
inspected,
no items of noncompliance
were
identified in three areas.
One item of noncompliance (failure to follow
procedures)
was identified in one area.
Region I Form 12
(Rev. April 77)
82i0090217 Bi0925"
i OR AOacv osoooaoe
8
DETAILS
Individuals Contacted
Princi al Licensee
Em lo ees
~B. A. Snow, Plant Superintendent
(telephone
only)
- D. Filkins, Supervisor,
Chemistry
and Health Physics
~D. Filion, Radiochemist
"W. Goodman,
Foreman,
Health Physics'nd
Chemistry
J.
Bodine,
QC Engineer
~J.C.
Noon, Assistant Superintendent
(telephone
only)
- E. Gordan,
Health Physicist
- F. Mis, Health Physicist
"B. Quinn, Health Physicist
- R Watts, Health Physicist
"denotes
those present at exit interview.
The inspector also interviewed other licensee
employees
including
member s of the chemistry,
health physics
and
QC staffs.
C
Licensee Action on Previous
Ins ection Findin
s
(Closed)
Inspector
Follow Item (50-244/78-19-01):
Calibration of
radioiodine
on charcoal
cartridge.
During
a previous inspection
(NRC
Inspection
Report 50-244/78-19)
the licensee's
measurement
of iodine
on
a charcoal
cartridge
was higher than the NRC's value
and in
disagreement.
The licensee's
measurements
of iodine
on
a charcoal
cartridge during this inspection
were in agreement with the NRC's
measurements.
Since Inspection
Report 50-244/78-19
the licensee
has
recalibrated
his Ge(Li) detector for iodine
on charcoal
cartridges.
See
Paragraph
5.
Laborator
C Pro
ram
The licensee's
QC program is detailed in Procedures
HP-10.1, Quality
Control of Counting Systems.
This procedure
provides for operational
checks of counting equipment including backgrounds,
source
checks
and
periodic chi-squared tests,
and where applicable
gain and resolution
checks.
The inspector
reviewed the licensee's
QC data for 1980
and
1981 to date
and determined that the licensee
was implementing his
program
as detailed in procedure
HP-10. 1.
The inspector discussed
various aspects
of
NRC Regulatory Guide 4. 15, Quality Assurance for
Radiological Monitoring Programs
(Normal Operations)
Effluent
Streams
and the Environment with the licensee.
'
~
~
With respect to nonradiological
chemistry quality control the
inspector
noted that the licensee
had
no specific program in this area
but
some of the licensee's
analytical
procedures
included steps to
ensure quality such
as the analysis of blanks
and
known standards
and
methods for reagent control.
No items of noncompliance
were identified in this area.
Audit Results
The inspector determined that the licensee's
effluent monitoring and
chemistry programs
were
on the corporate
gA audit list.
The inspector
reviewed audit 80-49:CA which was conducted
on December
9-10,
1980.
The inspector
had
no further questions
in this area.
No items of noncompliance
were identified.
Confirmator
Measurements
During the inspection,
actual liquid and gaseous
effluent samples
were
split between
the licensee
and the
NRC for the purpose of
intercomparison.
The effluent samples
were analyzed
by the licensee
using his normal
methods
and equipment,
and the
NRC using the
NRC: I
Mobile Radiological
Measurements
Laboratory.
Joint analyses
of actual
effluent samples
determines
the licensee's
capability to measure
radioactivity in effluent samples.
In addition,
a liquid effluent sample
was sent to the
NRC reference
laboratory,
Department of Energy, Radiological
and Environmental
Services
Laboratory (RESL), for analysis requiring wet chemi stry.
The
analyses
to be performed
on the
sample are:
gross alpha,
gross beta
and tritium.
These results will be compared with the licensee's
results
when received at
a later date,
and will be documented
in a
subsequent
inspection report.
The results of the
sample
measurements
comparison
indicated that all
of the measurements
were in agreement
or possible
agreement
under the
criteria used for comparing results;
(See Attachment 1.)
The results
of the comparisons
are listed in Table l.
Procedures
The inspector
reviewed the licensee's
effluent and analytical
chemistry procedures.
The inspector
noted that procedure
PC-18. 1,
Chloride Determination,
requires
a shelf life of 4 weeks for mercuric
thiocyanate
used in the analysis.
The mercuric thiocyanate
is used
for the chloride analysis of reactor coolant
samples.
During this
inspection
on March 18,
1981, the inspector
noted that the expiration
date
on the mercuric thiocyanate
was January
20,
1981.
The inspector
stated that the failure to follow procedure
PC-18. 1 with respect to
the mercuric thiocyanate
shelf life was
an item of noncompliance.
(81-
06-01)
The inspector
reviewed the results of other reactor coolant
chemical
analyses
for the period January to March,
1981 and noted that
there
were no'indications that any of the reactor coolant chemical
specifications
were exceeded.
Further,
a comparison of the, results of
the reactor coolant chloride analysis
performed using unexpired
mercuric thiocyanate
was in agreement with the results of an analysis
using the expired reagent.
The inspector
had
no further questions
in
this area.
7.
Exit Interview
The inspector
met with the licensee
representatives
(denoted
in
Paragraph
1) at the conclusion of the inspection
on March 19,
1981.
The inspector
summarized
the purpose
and
scope of the inspection
and
the inspector findings.
The licensee
agreed to perform the analyses
listed in Paragraph
5 and
report the results
to the
NRC.
TABLE 1
Ginna Verification Test Results
SAMPLE
ISOTOPE
NRC VALUE
LICENSEE VALUE
COMPARISON
Resul ts in Microcuries
er Milliliter
Reactor
Coolant
1159 hours0.0134 days <br />0.322 hours <br />0.00192 weeks <br />4.409995e-4 months <br />
3-17-81
I-133
I-135
(1. 39%. 03) E-2
(1. 285+0. 013) E-1
(2.2+O.l)E-l
(2. 07+0. 41) E-2
(1. 25+0. 07) E-1
(2.08+0.23)E-1
Possible
Aareement
Aqreement
Agreement
Reactor
Coolant
Crud
0148 hours0.00171 days <br />0.0411 hours <br />2.44709e-4 weeks <br />5.6314e-5 months <br />
3-12-81
Cr-51
RU-103
Cs-134
(3. 9K. 8) E-5
(2. 1+0. 3) E-6
(2.9+1.0)E-6
(8.5+1.8)E-6
(1.92+0.03)E-4
(2.48+0.03)E-4
(3.7+0.3)E-5
(2.440.6)E-6
(2.6+0.6)E-6
(1.13+0.07)E-5
(2.20+0.03)E-4
(2. 91+0.03) E-4
Agreement
Aareement
Agreement
Agreement
Agreement
Aqreement
~
~
~
'A
(sJ
'J,
7
E l
TAHLE 1
Ginna Verification Test Results
SAMPLE
ISOTOPE
NRC VALUE
LICENSEE VALUE
COMPARISON
Results in Microcuries
er Milliliter
Waste
Gas
Oecay
Tank
1356 hours0.0157 days <br />0.377 hours <br />0.00224 weeks <br />5.15958e-4 months <br />
3-17-81
Plant Vent
Charcoal
Cartridge
1129 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.295845e-4 months <br />
3-17-81
Waste Hold
Up Tank
1415 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.384075e-4 months <br />
3-17-81
Xe-135
I-133
Co-58
Ag-110m
Cs-134
(4.9+0.3)E-3
(3.38+0.05)E-3
(1. 7+1. 2) E-5
(9. 3+1. 0) E-14
(1.8+0.4)E-13
(1.4+0.1)E-5
(2. 1+0. 1) E-5
(1. 58+0. 03) E-4
(6.9+0.2)E-5
(5.4+0.2)E-5
(4.8+0.04)E-4
(4.4+0.7)E-3
(3.53+0.04)E-3
(1.9+0.2) E-5
(1.4+0. 1) E-13
(2. 1+0. 4) E-13
(9. 6+2.8) E-6
(1. 3+0. 3) E-5
(2.07+0.05)E-4
(7.8+0.6)E-5
(6. 1+0. 3) E-5
(4. 18+0. 08) E-4
Agreement
Agreement
Agreement
Agreement
Agreement
Agreement
Possible
Agreement
Possible
Agreement
Agreement
Agreement
Agreement
Attachment
1
Criteria for Com grin
Anal tical Measurements
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 judgement limits are variable in relation to the
comparison of the
NRC Reference
Laboratory's
value to its associated
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
must
be considered
acceptable
as the resolution decreases.
Resolution
<34-7
8 - 15
16- 50
51 - 200
>200
Agreement
0.4 - 2.5
0 '
- 2.0
0.6 - 1.66
0.75
1
~ 33
0.80 - 1.25
0.85 - 1.18
0.3 - 3.0
0.4
2.5
0.5
2.0
0.6
1.66
0.75
1.33
0.80 - 1.25
No Comparison
0.3 - 3.0
0.4
2.5
0.5 - 2.0
0.6 - 1.66
0.75 - 1.33
LICENSEE VALUE
RATIO= NRC
REFERENCE
VALUE
Possible
Possible
A~A
~A
"A" criteria are applied to the following analyses:
Gamma Spectrometry
where principal
gamma energy
used for identification
is greater
than
250 Kev.
Tritium analyses
of liquid samples.
Iodine on absorbers
"B" criteria are applied to the following analyses:
Gamma Spectrometry
where principal
gamma energy
used for identification
is less
than
250 Kev.
89Sr and 90Sr Determinations.
Gross
Beta where samples
are counted
on the
same
date using the
same
reference
nuclide.
'I
0
P
~ ~
0