ML19241B045
| ML19241B045 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/24/1979 |
| From: | Gibson G, Hufham J, Montgomery D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19241B033 | List: |
| References | |
| 50-269-79-08, 50-269-79-8, 50-270-79-08, 50-270-79-8, 50-287-79-08, NUDOCS 7907110596 | |
| Download: ML19241B045 (4) | |
See also: IR 05000269/1979008
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION 11
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101 M ARIE iTA STREET.N.W.
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ATLANTA, GEORGIA 30303
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keport No. 50-269/79-8, 50-270/79-8 and 50-287/79-8
Licensee: Duke Power Company
P. O. Box 2178
422 South Church Street
Charlotte, North Carolina 28242
Facility Name: Oconee 1, 2 and 3
License Nos. DPR-38 DPR-47 and DPR-55
Inspection at Ocon
Site near Seneca,
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Inspectorst
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D.' M. Mont omgry / '
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Date Signed
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Date Signed
Approved by:k
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. Huf ham, ye tion Chief, FFMS Branch
Date Signed
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SUtiMARY
Inspection on March 14-15, 1979
Areas Inspected
This routine unannounced inspectic.4 involved 36 insp'c wr-hours onsite in the
areas of confirmatory measurements including:
exac.im tion of laboratory
radiochemical equipment and instrumentation; review of quality control in
analytical measurements; collection of plant effluent samples for future
comparison of analytical results; and review of the chemistry and radio-
chemistry procedures.
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Results
Of the 4 areas inspectoed, no apparent items of noncompliance or deviations
were identified in 3 areas; I apparent item of noncompliance was found in 1
area (infraction - failure to follow calibration procedure, paragraph 8.b); I
apparent deviation was found in 1 area (failure to use a proper calibration
source, paragraph 8.c).
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DETAILS
1.
Persons Contacted
Licensee Employees
- J. H. Davis, Acting Plant Manager
- R. T. Bond, Licensing and Projects Engineer
- D. J. Vito, Licensing Engineer
- R. Koehler, Superintendent Technical Services
- C. Yongue, Health Physics Supervisor
- J.
Long,
Counting
Room
Supe rvisor
J. Lochamy, Health Physicist (Corporate Office)
h7C Resident Inspector
- F. Jape
- Atcended exit interview.
2.
Exit Interview
The inspection scope and findings were summarized on March 15, 1979,
with those persons indicated in Paragraph 1 above.
3.
Licensee Action on Previous Inspection Items
No previous enforcement items were examined during this inspection.
4.
Unresolved Items
Unresolved items are matters about which more informatica is required to
ascertain whether they are acceptable items, items of nonco,apliance, or
deviations. Two unresolved items disclosed during this inspection are
discussed in paragraph 8.d and 8.e of this report.
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5.
Instrumentation
The inspectors examined the chemistry and radiochemistry laboratories
and instrumentation.
The inspectors reviewed records for the daily
energy calibration of the GeLi gamma spectroscopy systems. The inspec-
tors verified that the counting equipment had been tagged according to
the procedures.
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6.
Review of Quality Control
The inspectors reviewed selected quality control records for instrumen-
tation including the beta gamma detector, the liquid scintillation
counter, and GeLi detectors.
The record review included background
counts, daily performance checks, efficiency checks, and control charts.
7.
Confirmatory Measurements
The inspectors arranged for the collection of following samples: waste
gas. particulate filter, charcoal cartridge, and a 1-L liquid waste
sample.
These samples were forwarded to the NRC reference laboratory, in Idaho
Falls, Idaho for analysis. The results will be compared with the licensee's
results during a subsequent inspection (269/79-08-01, 270/79-08-01,
287/79-08-01).
8.
Review of Chemistry and Radiochemistry Procedures
a.
The inspectors reviewed procedures for reactor coolant stable
chemistry including fluoride, chloride, boron, and dissolved oxygen.
The inspectors noted that the procedures had been reviewed and
approved as per Technical Specification 6.4.1.
b.
Technical Specification 6.4.1 requires the station to be operated
and maintained in accordance with approved procedures. The approved
Oconee procedure HP/0/B/1003/09, " Calibration Procedure for GeLi
Detectors on the ND 6620 Multichannel Analyzer", specifies that
standard radionuclide sources shall be used in normal sample geo-
metries for efficiency calibrationr. The inspectors were informed
on March 14, 1979, that contrary to the above, from March 1978
through March 1979, the GeLi efficiency calibrations were obtained
by using a procedure, other than HP/0/B/1003/09, which had not been
approved by the appropriate authority. The inspector reviewed the
calibration techniques utilized by the licensee in leiu of HP/0/B/
1003/09.
The inspecto rs ' dete rmined the procedural techniques
employed do not provide calibrations to NBS relatal
indards.
Discussions with USNRC Office of Inspection and Eni.
't, U.S.
Department of Energy Idaho Radiological Environments. nesearch
Labora tc ry, and the licensee's contractor, SAI, disclosed the
techniques employed have not been accepted by any reputable radio-
chemistry organization. Until such time as the technique has been
examined and approved by a reputable scientific body, this technique
is not considered in conformance with industry accepted standard
methods (see paragraph 8.e.).
This item constitutes an item of
noncompliance
with
the
referenced
Technical
Specification
(269/79-08-02, 270/79-08-02 and 287/79-08-02).
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c.
The inspectors reviewed the procedure for the calibration of the
beta gamma detector which is used for counting smears associated
with contamination control.
Licensee representatives confirmed
that a 9USr source on a platinum backing has been used for effi-
ciency calibrations, and that the average beta energy is much
higher than the beta energies from the most commonly encountered
radionucludes such as 137Cs and 6 Co.
The inspectors informed the
licensee that the 9 Sr efficiency may be as much as 3 to 4 times
greater than that obtained with the typical radionuclides such as
'37Cs and 6 Co.
The inspectors informed the licensee that this
could result in the release of material and equipment with contami-
nation lev-1s exceeding the control limit. Licensee representatives
indicated that a shipment of low-level solid waste barrels had been
loaded on a truck and was to be released on March 15, 1979, and
that they would resurvey the shipment to insure that applicable DOT
regulations would not be violated.
The inspectors informed the
licensee that this item was a deviation from ANSI Standard N-323-1978,
Section 4.3.2 which states " Calibrations shall be performed with a
standard source providing radiation fields similar to those in
which the instrument will be used.
(269/19-08-03, 270/79-08-03 and
287/79-08-03).
d.
The inspectors reviewed the procedure for operation of the liquid
scintillation counter and the certification of the tritium standard.
The inspectors informed the licensee that the certification was not
sufficient to ensure to accuracy of the standard since it did not
provide information regarding th- measurement method, the chemical
composition cf the standard, radionuclide impurities, or the supplier's
identification of the source. The licensee agreed to contact the
suppliar regarding the missing information.
This item shall be
considered an unresolved item (269/79-08-04, 270/79-08-04 and
287/79-08-04).
e.
The inspectors examined the procedure, ER/0/B/8000/04, "Geli Detector
Ef ficiency Calibration".
This method iuvolves cross calibration
with a reference detector located at the Duke Environmental Laboratory.
The NRC Regulatory Guides-l'.21 and 4.15, and ANSI Standard N42.14-1978
specify that efficiency calibrations for gamma spectroscopy systems
should be made with NBS standard solutions or equivalent standard
solutions in the same geometries as used for sample analysis.
Contrary to the above, the licensee developed and implemented the
procedure, ER/C 'B/8000/04 which does not use standards sources
prepared in the actual sample geometries. The new method was not
demonstrated to be equivalent to existing standard methods or to
provide calibrations with an accuracy equivalent to or better than
the plant approved procedure, HP/0/B/1003/09.
Ti.i s item shall be
considered an unresolved item (269/79-08-05, 270/79-08-05 and
287/79-08-05).
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