ML20154R365

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Insp Repts 50-338/88-26 & 50-339/88-26 on 880815-19.No Violations or Deviations Noted.Major Areas Inspected: Confirmatory Measurements & Counting Room QA for in-plant Radiochemical Analyses
ML20154R365
Person / Time
Site: North Anna  Dominion icon.png
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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  • 4 UNITED STATES

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NUCLEAR REGULATORY COMMISSION

o, .f REGION 11

101 MARIETTA ST., N.W.

% o,,,, f 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 License hos.: NPF-4 and NPF-7

Facility Name: North Anna 1 and 2

Inspe: tion Condu~ e? August 15 *_. acQ

Inspector:__"

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Accompanying Personnel: J. B. Kahle

, T. Volk

Approved by:

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Kanie. Section Chief

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0 .e signed

icn of Radiation Safety and Safeguards

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SUMMARY

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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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 .

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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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.

IN 88-22: Disposal of Sludge from Onsite Sewage Treatment Facilities at

Nuclear Power Stations

IN 81-31: 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.

For comparison purposes, a ratio 8 of the licensee value to the NRC value for

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