ML19276F161
| ML19276F161 | |
| Person / Time | |
|---|---|
| Site: | 07001201 |
| Issue date: | 03/01/1979 |
| From: | Silk E BABCOCK & WILCOX, BABCOCK & WILCOX CO. |
| To: | Sutherland J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML19276F155 | List: |
| References | |
| NUDOCS 7903270424 | |
| Download: ML19276F161 (3) | |
Text
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Babcock &Wilcox e..,cene,ation arca, P.O. Box 1260, Lynchburg, Va. 24505 Telephone: (804) 384-5111 March 1, 1979 oa 2:
United States Nuclear Regulatory Commission Region II c.n 101 Marietta Street, N.W.
Suite 3100
~
Atlanta, GA 30303 Co u
1 Attention:
Mr. J. T. Sutherland, Chief Fuel Facility 6 Materials Safety Branch
Reference:
RII:WJM, 70-1201/79-02 Gentlemen:
In the course of the referenced inspection conducted on January 15-19, 1979, one infraction and one deficiency were noted as discussed below:
A.
Infraction As required by License Condition 8.2.1, daily isokinetic samples of recirculated air shall be collected in the pelletizing area when the facilities are in operation.
Contrary to the above, on January 18, 1979, the pitot tube used to determine the proper flow rate through the sampling probe for isokinetic conditions was found to be oriented perpendicular to the air flow in the recirculation duct and was therefore providing erroneous information; also, the probe being used to collect a sample was oriented at an angle of approximately 45 degrees to the airflow. These conditions constitute anisokinetic sampling.
Response
As noted in the body of the inspection report, this item was prompty corrected in the inspector's presence and has not recurred since that time.
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Babcock &VVilcox United States Nuclear Regulatory Commission Page 2 March 1, 1979 A.
Response (continued)
Since the inspection report alleges that the sampling system as inspected would provide erroneous information regarding quantity of radionuclides released, a comparison was made of the stated release quantities before and after system modifi-cation.
Both two-week periods were chosen on the basis of fuel fabrication activity level so that parallel data compari-sons could be made.
Based on a statistical t-test of mean daily activity released for a two-week period prior to the modification and a corresponding two-week period subsequent to the modification, we have concluded that the quantity of radio-nuclides stated under either condition are statistically equivalent at the 99% confidence level.
Therefore, we request that this apparent item of noncompliance (infraction) be reevaluated and appropriate corresponding action be taken.
To prevent future recurrence of the situation, the probes were properly adjusted and secured in position, and will also be checked periodically to verify alignment.
Full compliance has been achieved prior to completion of the inspection.
B.
Deficiencg As required by 10 CFR 70.59 each licensee authorized to possess and use special nuclear material for fuel fabrication shall sub-mit a report to the appropriate NRC Re/ional Office within 60 days after January 1 and July 1 of each year specifying the quantity of each of the principal radionuclides released to unrestricted areas in gaseous effluents during the previous six months of operation.
Contrary to the above, the licensee has not, at any time since its installation in April 1976, reported the quantity of each of the principal radionuclides released to unrestricted areas in gaseous effluents from the damper on the pelletizing recirculation system.
Response
Based on conversations with the inspector, conservative assumptions were made regarding the quantity of principal radionuclides released from the damper system.
These values were applied to the semi-annual
Babcock &VVilcox United States Nuclear Regulatory Commission Page 3 March 1, 1979 B.
Response (continued) report submitted to NRC on February 2,1979, covering the period of July-December, 1978.
Full compliance was achieved on January 29, 1979 when the appropriate equipment items were received and installed to permit measurement of total radionuclides released.
Consequently, the next semi-annual gaseous effluent report covering the January-June 1979 period will be based on conservative assump-tions prior to January 29, 1979, and actual measurements subsequent to that date.
No n., terial of a proprietary nature is discussed in the report.
We will be glad to meet with you to discuss these items further if you desire.
Sincerely, BAB CK 6 WILCOX COMPANY
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E. J. Silk, nan [ger C <mercial Nuclear Fuel Plant EJS:cm cc:
D. W. Zeff
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