ML20154R365
| ML20154R365 | |
| Person / Time | |
|---|---|
| Site: | North Anna |
| Issue date: | 09/20/1988 |
| From: | Bermudez H, Kayle J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20154R357 | List: |
| References | |
| 50-338-88-26, 50-339-88-26, NUDOCS 8810040236 | |
| Download: ML20154R365 (10) | |
See also: IR 05000338/1988026
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION 11
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101 MARIETTA ST., N.W.
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ATLANTA. GEORGIA 30323
SEP 211NB
Report Nos.:
50-338/88-26 and 50-339/88-26
Licensee:
Virginia Electric and Pcwer Company
Richmond, VA 23261
Docket Nos.:
50-335 and 53-339
Facility Name:
North Anna 1 and 2
Inspe: tion Condu~ e?
August 15 *_.
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Inspector:__" e rmuce_
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Accompanying Personnel:
J. B. Kahle
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T. Volk
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Approved by:
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Kanie. Section Chief
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icn of Radiation Safety and Safeguards
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SUMMARY
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Scope:
This routire, announced inspection was conducted in the areas of
Confirmatory Measurements and Counting Room Quality Assurance fer in plant
radiochemical analyses.
Results: Overall, the NRC's and the licensee's measurments were in agreement.
Biases on the high side were noted in several counting geometries.
The licensee
was in the pro:ess of caliorating the garma spe:tremetry systems at the time of
the inspection.
The licensee agreed to orovide Region II with the new
calibration data for review and evaluation to determire the comparison of
cuunting data with the new calibration against hRC measurements. No violations
or deviations were identified.
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REPORT DETAILS
1.
Perscns Contacted
Licensee Employees
- E. Oreyer, Supervisor, Health Physics
- R. Ortscoll, Manager, Quality Assurance
- G. Kane, Station Manager
- P. Kemp, Licensing Coordinator
- K. LeFevre. Sr. Health Physicist (Corporate)
- D. VandeWalle, Supervisor, Licensing
M. Young, Counting Room Technician
Other licensee employees contacted included technicians, security of fice
members, and office personnel.
NRC Resident Inspectors
- J. Caldwell
L. King
"Attended exit interview
2.
Licensee Action on Previous Enforcement Matters
This subject was not addressed in the inspection.
3.
Confirmatory Measurements (84725)
During the inspection, reactor coolant, a particulate filter, charcoal
cartridges and selected liquid and gaseous samples were obtained by or
orovided to the licensee for analysis by their gamma spectrometry systems.
The licensee's results were compared against those obtained by the
inspector from the same samplas analy:ed by the NRC Region II Mobile
Laboratory gamma spectrometry system.
The purpose of these comparative
measurements was to verify the licensee's capability to accurately
identify and quantify gamma-emitting radionuclides in various plant
systems and ef fluent streams.
Comparisons were made against the three
oetectors located in the licensee's health physics counting room.
Sample types compared included the following:
(1) degassed reactor
coolant, (2) reactor coolant gas (3) waste gas decay tank (4) simulated
liquid waste (licensee-spiked), (5) plant stack charcoal cartridge (for
iodine determinations), (6) spiked charcoal cartridge (provided by the
NRC) and (7) spiked particulate filter (oroviced by the NRC).
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2
A more detailed description of the sample types and counting geometries
along with a comparison of the NRC and licensee results is listed in
Attachment 1.
The retnodology for determining agreement with licensee
results is discussed in Attachmant 2.
Approximately two months crior to this inspection. the licensee was informed
by its Corporate Of fice of the results of a recent cross-cneck stucy of
radiation measurement capabilities among the ccmpany's f acilities.
The
results of that study showed that the licensee had been overestimating
activities in the particulate filter geometry.
The licensee then began
recalibrating the gamma spectrometry systems and investigated the cause of
the disagreements. At the time of the inspection, licensee representatives
indicated that the most likely cause of the disagreements was a defective
balance used during tne preparation of the calicration stan0ards.
Since the new calibration parameters had not been officially incorporated
.
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into the counting room operations, the inspector tested the performance
of the gamma spectrometry systems using the current (old) calibration
parameters.
Results indicated disagreements anc biases on the high side for the
particulate filter geometry. High results were also noted in the 100 mi
liquid Marinelli and charcoal cartridge aeometries. Much closer agreement
was obtained in the gas chamber and 100 ml liquid geometries.
Initial disagreements associated with cadmium-109 (Cd-109) determinations
were attributed to the licensee's use of an older version of computer
software.
The sof tware's library reflected a gamma cecay abundance of
approximately 5% while the newer version being currently installed showed
an abundance of approximately 3.8%.
Disagreements in Cd-109 determinations
were resolved as soon as licensee representatives incorporated the updated
abundance values into the software.
Disagreements in the determinations of mercury-203 (Hg-203) ir, the charcoal
cartridge gecretry were attributed to a substantial difference between the
old and the new calculated deto; tion efficiencies for tnat particular
radioisotope. The inspector determined that disagreement in Hg-203 deter-
minations in the charco31 cartridge geometry was not safety-significant
since the licensee only used charcoal cartridges for radiciodine deter-
l
minations, and there were no disagreements in iodine results otner than
noted biases on the high side.
The inspector requested that the licensee provided the NRC with the new
calibration data for analysis to determine whether closer agrecment
cetween licersee and NRC values may be obtained.
Licensee management
agreed to the inspector's request. The inspector indicated that analysis
ard evaluation of the new calibration data will be considered an I soector
Folic 4up Item (IFI) (50-33E.339'65-2(-01).
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3
The inspector witnessed the sampling of reactor coolant and gaseous waste
decay tanks and determined that sampling techniques and health physics
practices were adequate.
No violations or deviations were identified.
3.
Quality Assurance - Counting Room Operations
The inspector reviewed quality control data for the licensee's gamma
spectrometry . sys tems , liquid scintillation counter and gas-flow propor-
tional counters.
Data reviewed included the gamma spectrometer, Beckman
LS-100C (liquid scintiliation counter) and NMC/PC-5 (alpha-beta counter)
daily performance test data for the period July - August 1988.
The inspector also reviewed current voltage plateau determinations for the
gas-flow proportional counters, the current annual calibration data
package for the gamma spectrometers and the sample logbook.
The inspector verified that standards used during performance tests and
calibrations were traceable to the National Bureau of Standards (NBS).
However, due to the problems encountered during the previous calibration of
the gamma spectrometry systems, the inspector discussed with cogni: ant
licensee management the benefits of cross-checking the accuracy of the
calibration standards prepared from NBS-traceable standards.
The inspector
referred licensee representatives to Regulatory Guide 4.15, "Quality
Assurance for Radiological Monitoring Programs (Normal Operations) -
Ef fluent Streams and the Environment," February 1978, for guidance.
The inspector also reviewed the most recent audit of the health physics
program performed by the licensee's Corporate Office.
A very small
portion of the audit covered counting room operations.
The audit was
general and lacked depth to be able to identify weaknesses in the
licensee's health physics program.
No violations or deviations were identified.
4.
Followup on Information Notices (92701)
The inspector determined that the following Information Notices (ins) had
veen received by the licensee, reviewed for applicability, distributed to
appropriate personnel and that action, as appropriate, was taken or
scheouled.
Disposal of Sludge from Onsite Sewage Treatment Facilities at
Nuclear Power Stations
Steam Generator Tube Rupture Analysis Deficiency
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5.
Exit Interview
The inspection scope and finJings were summari:ed on August 19, 1938, with
those persons indicated in Paragraph 1 above. The inspector described the
areas inspected and discussed in detail the inspectiri findings.
No
dissenting comments were received from the licensee.
This licensee did not identify as proprietary any of the material provided
to or reviewed by the inspector during this inspection.
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ATTACHMENT 2
CRITERIA FOR COMPARING ANALYTICAL 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 denoting agreement or disagreement
between licensee and NRC results are variable. This variability is a function
of the NRC's value relative to its associated uncertainty, referred to in this
program as "Resolution"1 trcreases, the range of acceptable differences between
the NRC and licensee values should be more restrictive.
Conversely, poorer
agrement between NRC and licensee values must be considered acceptable as the
resolution decreases.
8 of the licensee value to the NRC value for
For comparison purposes, a ratio
each individual nuclide is computed.
This ratio is then evaluated for
agraement based on the calculated resolution. The corresponding resolution and
calculated ratios which denote agreement are listed in Table 1 below.
Values
outside of the agreement ratios for a selected nuclide are considered in
disagreement.
- Resolution = NRC Reference Value for a Particular Nuclide
Associated Uncertainty for the Value
8 Comparison Ratio = Licensee Value
NRC Reference Value
TABLE _1_
Confirmatory Measurements Acceptance Criteric
Resolutions vs. Comparison Ratio
Comparisons Ratio
for
Resolution
Acree-ent
<4
0.4 - 2.5
4-7
0.5 - 2.0
3 - 15
0.6 - 1.66
16 - 50
0.75 - 1.33
51 - 200
0.80 - 1.25
>200
0.85 - 1.18
.
t