ML17053C865
| ML17053C865 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 09/03/1981 |
| From: | Bores R, Jang J, Kottan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17053C862 | List: |
| References | |
| 50-220-81-07, 50-220-81-7, NUDOCS 8110060279 | |
| Download: ML17053C865 (14) | |
See also: IR 05000220/1981007
Text
U.S.
NUCLEAR REGULATORY COMMISSION
OFFICE
OF INSPECTION AND ENFORCEMENT
Region I
Report
No. 50-220/81-07
Docket No. 50-220
License
No.
Pri ority
Category
C
Licensee:
Nia ara
Mohawk Power Cor oration
300 Erie Boulevard West
S racuse
13202
Facility Name:
Nine Mile Point Nuclear Station
Unit
1
Inspection At:
Lycoming,
Inspectors
Inspect,ion
Conducted:
Mar
h 23-25,
1981
J.J.
Kottan,
a iation Laboratory Specialist
J
. Jang, Rad'ion Specialist
date
signed
date
signed
Approved By: ~J.
Chief, Independent
Measurements
and Environmental
Protection
Section
date
signed
g-8
date
signed
Ins ection
Summar
Ins ection
on March 23-25
1981
Re ort No. 50-220/81-07
Areas
Ins ected:
Routine,
unannounced
inspection of the licensee's
chemical
and radiochemical
measurements
program using
NRC: I Mobile Radiological
Measurements
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 effluent
control
and analysis
procedures;
The inspection
involved 30 inspector-
hours onsite
by two
NRC regional
based
inspectors.
Results:
Of the'our areas
inspected,
one item of noncompliance
(Failure
to approve
procedures-Paragrah
5) was identified in one area.
Region I Form
12
(Rev. April 77)
Biioo~o~< OgOOOQ20,
)
9 81091~
poR
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DETAILS
1.
Individuals Contacted
Princi al Licensee
Em lo ees
~J.
Duell, Radiation Protection-Chemistry
Supervisor
E.
Leach,
Chemistry
and Radiation Protection
Superintendent
- J.
Blasiak, Assistant
Supervisor
Radiation Protection-Chemistry
- T.
Kartz, Assistant Supervisor Radiation Protection-Chemistry
- M.
Si lliman, Technical
Superintendent
K.
Shea,
Assistant
gC Technician
The inspector also talked with and interviewed other licensee
employees
including members of the chemistry
and health physics staffs.
- Denotes those present at'xit interview.
2.
Laborator
C Pro
ram
The inspector
reviewed the licensee's
program for the quality control
of analytical
measurements.
The
gC program is detailed in Section II
of Yolume IV of the Site Chemistry
and Radiation Protection
Manual.
The licensee's
gC program consists
of approved
procedures,
traceable
standards,
reagent control, periodic instrument calibration
and checks
and periodic split samples.
The inspector
reviewed the licensee's
gC
data for 1980 and through February
1981.
The inspector also discussed
laboratory
gC with the licensee
in general,
and various aspects
of
Regulatory
Guide 4. 15, guality Assurance for Radiological Monitoring
Program
(Normal Operations)-Effluent
Streams
and the Environment.
No items .of noncompliance
were identified.
3.
Audit Results
The inspector determined that the licensee's
chemistry/radio-chemistry
program
was
on the
gC audit list.
The inspector
reviewed audits
SR-
80-022 dated October 7,
1980
and SR-80-050,
dated
December
10,
1980.
The inspector
had
no further questions
in this area.
No items of noncompliance
were identified.
e
e
1
Confirmator
Measurements
During the inspection,
actual liquid and gaseous
effluent samples
were
split between
the licensee
and NRC:I 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
determine
the licensee's
capability to measure
radioactivity in effluent
samples.
During this inspection,
however,
a simulated off gas
standard
was
given to the licensee
because
the facility was
shutdown during the
inspection.
In addition,
a liquid effluent sample
was sent to the
NRC reference
laboratory,
Department of Energy, Radiological
and Environmental
Services
Laboratory (RESL), for an analyses
requiring wet chemistry.
The analyses
to be performed
on the
sample are:
Sr-89, Sr-90,
gross
alpha,
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
compared,
indicated that all
of the measurements
were in agreement,
or possible
agreement,
under
the criteria used for comparing results.
(See Attachment I).
The
results of the comparisons
are listed in Table I.
Procedures
The inspector
reviewed the licensee's
procedures
for effluent control
and analyses.
The inspector
noted that the licensee
has tritium and
strontium 89 and
90 analyses
of effluents performed
by a contracting
laboratory.
The licensee,
however,
does not have copies of their
contractor's
procedures,
nor have the contracting laboratory's
procedures
been
approved
by the licensee
as required
by Section 5.5.2 of the
Environmental
Technical Specifications.
The inspector stated that
failure to have
a written Site Operations
Review Committee
(SORC)
approved,
contracting laboratory procedure for tritium and strontium
89 and
90 as required
by sections
5.5. 1 and 5.5.2 of the Environmental
Technical Specifications
was
an item of noncompliance
(81-07-01).
The
inspector
noted,
however, that Sr-89
and Sr-90 comparisons
made
from
samples split during previous inspections
were in agreement.
The inspector
had
no further question
in this area.
~
I ~
'TABLE 1
Nine Mile Point - Verification Test Results
SAMPLE
ISOTOPE
NRC VALUE
LICENSEE VALUE
COMPARISON
Results
in Microcuries
er Milliliter
Reactor Water
1300 hrs
3-23-81
Co-58
-Cs-134
(3. 1+0.4) E-6
(9. 36+0. 13) E-5
(4.79+0.08)E-5
(3.00+0.02)E-4
(6.3+0.5)E-6
(3.6+0.4)E-6
(1.06+0.02)E-4
(5.24m.09)E-5
(3.36+0.02)E-4
(7.0+0.5)E-6
Aoreement
Agreement
Agreement
Agreement
Agreement
Rad Waste
1300 hrs
3-23-81
Co-58
Fe-59
Cs-134
(1.37+0.05)E-4
(4.8~.4)E-5
(3.1+0.8)E-5
(1. 45+0. 05) E-4
(4.7+0.4)E-5
(2.7+0.4)E-5
(4.89+0.07)E-4
(5.28+0.08)E-4
(3. 071+0. 015) E-3
(3. 15+0.02) E-3
(1. 316%. 013) E-3
(1. 50+0.01) E-3
Agreement
Agreement
Agreement
Agreement
Agreement
Agreement
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TABLE 1
Nine Mile Point
Verification Test Results
SAMPLE
ISOTOPE
NRC VALUE
LICENSEE VALUE
COMPARISON
Results
in Microcuries
er Milliliter
Stack Particulate
Filter
0732 hrs
3-12-81
Cr-51
Co-58
(2.5%0. 2)E-12
(l. 88~0.05) E-12
(6.7+0.4)E-13
(4.17+0.08)E-12
(4. 2+0. 9) E-12
(2.6%0.3)E-12
(1.0+0.2)E-12
Possible
Agreement
Possible
Agreement
Possible
Agreement
(5. 12+'? ) E-12
Agreement
Stack Charcoal
Cartridge
0732 hrs
3-12-81
(4.2+0.2)E-12
(5. 3+0. 3) E-12
Agreement
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0
TABLE 1
Nine Mile Point - Verification Test Results
SAMPLE
-ENERGY
KeV
NRC VALUE
LICENSEE VALUE
COMPARISON
Results in Gammas
er Minute
NRC Simul ated
Off Gas
Sample*
81
303
346
356
779
964
1408
(2.65+0.14)E
5
(1.47+0.09)E
5
(2.62+0.15)E
6
(4.4+0.3)E
5
(1.26+0.08) E 6
(1.41+0.08) E 6
(2.00+0. 15)E
6
(4.08+?)E
5
(1.64+?)E
5
(3.22+?)E
6
(5.91+?)E
5
(1.36+?)E
6
(1.55+?)E
6
(2.18+?)E
6
Possible
Agreement
Agreement
Aqreement
Possible
Aoreement
Agreement
Agreement
Agreement
- At the time of the inspection,
the licensee's facility was shut down, and, therefore,
no off gas
sample
was available.
An NRC simulated off gas
sample
was given to the licensee.
The results
for the various photo peaks in the spectrum were compared in gammas
per minute emitted from the
sample.
0
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.
LICENSEE VALUE
RATIO= NRC
REFERENCE
VALUE
Resolution
c34-7
8-15
16- 50
51
200
>200
Agreement
0.4 - 2.5
0.5 - 2.0
0.6
1.66
0'5 - 1.33
0.80 - 1.25
0.85 - 1.18
Possible
A reement
A
0.3
3.0
0.4
2. 5
0.5 - 2.0
0.6
1. 66
0.75 - 1.33
0.80 - 1.25
Possible
A reement
B
No Comparison
0. 3
3.0
0.4 - 2.5
0.5 - 2.0
0.6 - 1.66
0.75 - 1.33
"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.
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