ML17308A248
| ML17308A248 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 06/30/1986 |
| From: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17308A247 | List: |
| References | |
| 50-335-86-09, 50-335-86-9, 50-389-86-08, 50-389-86-8, NUDOCS 8607290012 | |
| Download: ML17308A248 (3) | |
Text
NOTICE OF VIOLATION Florida Power and Light Company Docket Nos.
50-335 and 50-389 St.
Lucie Units 1 and 2
License Nos.
DPR-67 and NPF-16 EA 86-95 During a Nuclear Regulatory Commission (NRC) inspection conducted on April 14-18, 1986, violations of NRC requirements were identified.
The violations involved two failures to transfer radioactive material in accordance with regulatory requirements and one deficiency in your radiation protection program.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions,"
10 CFR Part 2, Appendix C ( 1986),
the violations are listed below:
10 CFR 71.5 requires that licensees who transport licensed material outside the confines of their plants or other place of use, or who deliver licensed material to a carrier for transport, comply with the applicable requirements of the regulations appropriate to the mode of transport of the Department of Transportation in 49 CFR Parts 170 through 189.
49 CFR 173.441(a) states that except as provided in 49 CFR 173.441(b),
each package of radioactive materials offered for transportation shall be designed and prepared for shipment so that under conditions normally incident to transportation the radiation level does not exceed 200 millirem per hour at any point on the external surface of the package.
Contrary to the above, on December 13,
- 1985, the licensee shipped two boxes of radioactive materials, Box No.85-105 and Box No.85-112, to a land disposal facility at Barnwell, S.
C. with dose rates of 250 and 400 milli-rem per hour, respectively, on the external surfaces of the packages.
The exceptions of 49 CFR 173.441(b) did not apply because the shipment was not made in an enclosed vehicle.
This is a Severity Level III violation (Supplement V).
10 CFR 71.5 requires that licensees who transport licensed material outside the confines of their plants comply with the applicable requirements appropriate to the mode of transport of the Department of Transportation (DOT) 49 CFR Parts 170 through 189.
49 CFR 173.425(b)( 1) requires that packaged shipments of low specific activity (LSA) material consigned as exclusive use must be packaged in a
DOT Specification 7A Type A package or in a strong, tight package so that there will be no leakage of radioactive material under conditions normally incident to transportation.
Contrary to the above, the licensee failed to package a shipment of LSA radioactive material in a DOT Specification 7A Type A package or a strong, tight package in that on October 22,
- 1985, shipment No. 85-49 arrived at the burial facility with a hole in one B-25 metal box.
This is a Severity Level IV violation (Supplement V).
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10 CFR 20. 103(c)(2) provides in part that the licensee may make allowance for use of respiratory protective equipment in estimating exposures of individuals to radioactive materials in air provided that the licensee maintains and implements a respiratory protection program that includes, as a minimum, written procedures regarding supervision and training of personnel and maintenance of records.
Contrary to the above, on April 18,
- 1986, the NRC inspector noted the licensee was making allowance in its Maximum Permissible Concentration hour assignment records for use of respiratory protective equipment in estimating exposures of individuals to radioactive material in air for purposes of determining compliance with 10 CFR 20. 103.
- However, the licensee did not have written procedures regarding maintenance of records showing that an individual had been issued a respirator.
This is a Severity Level IV violation (Supplement IV).
Pursuant to the provision of 10 CFR 2.201, Florida Power and Light Company is hereby required to submit to this office within 30 days of the date of this Notice a written statement of explanation in reply including for each violation:
(1) admission or denial of the violation, (2) the reason for the violation if
- admitted, (3) the corrective steps which have been taken and the results
- achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will be achieved.
Where good cause is
- shown, consider ation will be given to extending response time.
FOR THE NUCLEAR REGULATORY COMMISSION Ori g inal Si gned by Roger D. Mal ker Dated at Atlanta, Georgia, this/ day of June 1986.
J.
Nel son Grace Regional Administrator