ML19094A512
| ML19094A512 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/30/1977 |
| From: | Stallings C Virginia Electric & Power Co (VEPCO) |
| To: | O'Reilly J NRC/IE, NRC/RGN-II |
| References | |
| IR 1977031 | |
| Download: ML19094A512 (2) | |
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VntoINIA ELECTRIC A:;n Pov>'ER Co:!>iPANY RICHMOND,-VIIlGINIA 23261 December 30, 1977 Hr. JDJ::les P. OiReilly, Dir~ctor Office Of Inspection and Enforcement
- u. s. Nuclear Regulatory Commission Regiou II - Suite S18 230 Peachtree Street, Northwest Atlanta, Georgia 30303
Dear Mr. O'Reilly:
Serial 1,o. 573/l20i17
'?0&..'1/DL.B mbh Docket Nos. 50-280 50-281 Licenoe Nos. DPR-32 DPR-:H Thia ie in response to your letter of Dece:ilber 7, 1977. in rafer-ence to the inspection conducted ~t Surry Power Station on October 25-28, 1977,
.'llld reported in I.E. Inspection P.eporta 50-280/77-31 and 50-281/77-31.
We have revie\\.'ed your letter and the enclosed inspection report.
Our response to the specific nou-complianee item ia contained in the ettach-me..~t to this letter.
We have determined that no proprietary information is contained in the reports. Accordingly, the Virginia Electric and Fower Company inter-poses no objection to these inspection reports being ma.de a matter cf public disclosure.
Attachment:
5 copies cc: Mr. Robert W. Reid Very truly yours,
!fl. }2'?. xfjad, ;,,c;a/
C. u. Stallings Vice President - Power Supply and Production Operation3 780040062
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L 7...: :..-..*.. ~~ i RESPONSE TO DEVIATION LISTED IN IE INSPECTION REPORT NOS. 50-280/77-31, 50-281/77-31 NRC COMMENT 0
Based on the results of an NRC inspection conducted October 25-28, 1977, it appears one of your activities was not conducted in conformance with gen-erally accepted industry practice as indicated below.
NCRP Report No. 10, "Radiological Monitoring :Methods and Instruments,"
section 8 discusses beta-gamma radiation detectors.
Section 8.1 states, "A detecting Jnstrument should be used for locating sources of radiation and contamination, It shall not be used for measurement of the radiation unless it has been calibrated under appropriate conditions with radiation of approx-imately the same energy distribution as that being measured".
Contrary to the above detectors used to measure contamination have not been calibrated with a reference radioactive source.
Efficiency factors nec-essary to calculate contamination levels, are based on manufacturers data and appear to be in error based on independent measurements of efficiency by an NRC inspector on November 1, 1977.
These detectors are used to measure con-tamination of personnel, respirators, various tools and equipment, and to iden-tify contaminated areas of the plant.
RESPONSE
The deviation listed above is correct as stated in the inspection reports.
Specifically, pursuant to section 2.201 of the NRC'S "Rules of Practice",
Part 2, Title 10, Code of Federal Regulations, the following information is submitted:
- 1.
- 2.
- 3.
Corrective steps which have been taken and results achieved.
A preliminary study was conducted to determine the validity of using the 25% efficiency value for the HP-210 probe.
It has been determined that the 25% value was based on using 90sr-90y as a check source.
Using a 99Tc check source has been approximately 10%.
A NBS traceable 99Tc check source has been ordered to check the HP-210 probe effici-ency during instrument calibration period.
Corrective steps which will be taken to avoid further deviations.
Upon receipt of the 99Tc source the proper efficiency value will be determined.
All HP-210 probes will-then be checked and marked to indicate they have been checked with a source.
The correct effi-ciency value will be used and the appropriate procedures modified.
Date corrective actions will be completed.
I Upon receipt of the 99rc source.