ML17338A411
| ML17338A411 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 11/06/1978 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17338A407 | List: |
| References | |
| 50-250-78-21, 50-251-78-21, NUDOCS 7812280344 | |
| Download: ML17338A411 (3) | |
Text
NOV 06 1978 APPENDIX A NOTICE OF VIOLATION Florida Power and Light Co.
License Nos.
DPR-31 DPR-41 Based on the results of the NRC inspection conducted on September 11-15, 1978, it appears that certain of your activities were not conducted in full compliance with NRC requirements as indicated below.
These items have been categorized as described in our correspondence to you dated December 31, 1974.
A.
Technical Specification 6.11 states, in part, that procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR 20 and shall be adhered to for all operations involving personnel radiation exposure.
Procedure HP-66, "Issuance and Control of Respiratory Protection Equipment," requires, in part, that prior to personnel being issued respiratory equipment, the Health Physics Shift Supervisor, or his designee, ensure that the personnel have been properly trained and found to be medically certified to wear a respirator.
Contrary to the above, the inspectors observed the following instances where the requirements of approved radiation protection procedures were not being adhered to:
l.
On September ll, 1978, respirators F-98 and F-138 were issued to to an individual who was not medically certified to wear a
respirator.
2.
On August 31, 1978, respirators F-111, F-285, F-153, F-42, F-25, F-164, and F-05 were issued to a corporation name rather than a trained, medically certified individual.
Numerous examples of corporate issuance were noted by the inspector for the month of August, 1978.
This is an infraction.
B.
10 CFR 71.12b(ii) requires, in part, that the persons using shipping containers, pursuant to the general license, for which a certificate of compliance has been issued, comply with the terms and conditions of the certificate.
Certificate of Compliance No. 9113 for the Model No. 7-100 shipping container authorizes the use of the container under the general license provisions of 10 CFR 71.12(b);
and requires that (1) the contents of the secondary container meet the requirements of low specific activity radioactive material, defined in 10 CFR 71.4.(g).(i), (ii) 8 (iii), (2) the maximum total weight of the contents and secondary container shall not exceed 7000 pounds, and (3) lid lifting lugs shall not be used for lifting the cask and shall be covered in transit.
0'
AOV 0e We Appendix A
otice of lliolation License Nos.
DPR-31 DPR-41 Contrary to the above, records of dewatered spent resins shipped from the site on July 21 and 28, 1978, and August 25 and 31, 1978, state that greater than 7000 pounds were shipped on August 25 and 31, 1978 in a Model No. 7-100 shipping container and by calculations from the recorded data, indicate that greater than LSA concentrations for Group II materials (Mixed Fission Products) had been shipped for all the above shipments.
On September 12, 1978, a truck in transit was seen by the inspectors leaving the radiation controlled area with a Model No. 7-100 shipping container on a trailer with the lid lugs uncovered.
This is an infraction.
C.
Technical Specification 6,13.l.b states that "each high radiation area in which the intensity of radiation is greater than 1000 mrem/hr shall be subject to the provisions of 6.13.1(a) and, in addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under administrative control."
.Contrary to the above,
'on'September 12, 13, and 14, 1978, radiation levels in two high radiation areas inside reactor containment exceeded 1000 mrem/hr and no locked doors were provided for these individual areas.
The areas were:
18 inches from regenerative heat exchangers where levels ranged from 1000 to 3000 mrem/hr, and 18 inches from reactor cavity filters where levels ranged from 1500 to 2500 mrem/hr.
The reactor was shut down and the areas were accessible to service personnel.