ML14175B393
| ML14175B393 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 06/18/1986 |
| From: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14175B392 | List: |
| References | |
| 50-261-86-09, 50-261-86-9, EA-86-101, NUDOCS 8607070148 | |
| Download: ML14175B393 (3) | |
Text
NOTICE OF VIOLATION Carolina Power and Light Company Docket No. 50-261 H. B. Robinson, Unit 2 License No. DPR-23 EA 86-101 During the Nuclear Regulatory Commission (NRC) inspection conducted on April 7-11 and May 16, 1986, violations of NRC requirements were identified. The violations involved failures to comply with regulations applicable to the transportation and transfer of licensed material and failure to post and control a high radiation area.
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:
A.
10 CFR 20.311(d)(1) requires that licensees who transfer radioactive waste to a land disposal facility prepare all wastes so that the waste is classified according to 10 CFR 61.55.
10 CFR 61.55, Table 2, Column 1, specifies that the Class A concentration limit for Strontium-90 is 0.04 curies per cubic meter.
Contrary to the above, on July 31 and August 1, 1985, the licensee failed to classify radioactive waste transferred to a land disposal facility according to 10 CFR 61.55 in that several radioactive waste packages classified as Class A within shipment numbers OT-85-6 and OT-85-7 contained Strontium-90 concentrations in excess of 0.04 curies per cubic meter.
B.
10 CFR 71.5(a) requires that each licensee who transports licensed material outside of the confines of its plant or other place of use comply with the applicable requirements of the regulations appropriate to the mode of transport of the Department of Transportation (DOT) in 49 CFR Parts 170 through 189.
49 CFR 173.425(b)(1) requires that Low Specific Activity (LSA) materials consigned as exclusive use be packaged in DOT Specification 7A Type A packages or in strong, tight packages so that there will be no leakage of radioactive material under conditions normally incident to transportation.
Contrary to the above, on November 14, 1985, LSA radioactive material consigned as exclusive use within shipment number D-85-20 was not packaged in a DOT Specification 7A Type A package or in a strong, tight package.
A hole was found in the bottom of the package upon its arrival at the Chem-Nuclear Systems, Incorporated low level radioactive waste disposal site near Barnwell, South Carolina, and some of the nonradioactive package contents had leaked onto the trailer bed.
8607070148 860618 PDR ADOCK 05000261 PDR
- 2 C.
10 CFR 30.41(c) requires that no licensee transfer byproduct material except as authorized pursuant to that section.
10 CFR 30.41(b)(5) only permits the transfer of byproduct material to a person authorized to receive such byproduct material under terms of a specific or general license or their equivalent issued by the Commission or an Agreement State.
Condition 8.B of the State of Maryland radioactive material license number MD-31-076-01, Amendment 8, July 8, 1980, issued to Science Applications International (SAI) requires that each sample possessed by SAI not contain in excess of one millicurie of radioactive material.
Contrary to the above, on February 13, 1986, the licensee transferred a reactor coolant system filter sample to SAI for analysis which contained 12.73 millicuries of radioactivity.
Collectively, these violations have been evaluated as a Severity Level III problem (Supplement V).
D.
Technical Specification 6.13.1.a requires that each High Radiation Area in which the intensity of radiation is greater than 100 millirem per hour but less than 1000 millirem per hour be barricaded and conspicuously posted as a High Radiation Area and entrance thereto be controlled by issuance of a Radiation Work Permit. Each individual or group of individuals permitted to enter such areas shall also be provided with a radiation monitoring device which continuously indicates the radiation exposure rate in the area.
Contrary to the above, on April 8, 1986, the licensee failed to barricade and post as a High Radiation Area and to provide the other specified access controls for an area in the vicinity of the safety injection piping in the middle pipe gallery of the auxiliary building where the intensity of radiation at eighteen inches from the piping was approximately 180 millirem per hour.
This is a Severity Level IV violation (Supplement IV).
Pursuant to the provisions of 10 CFR 2.201, Carolina Power and Light Company is hereby required to submit to this Office within 30 days of the date of the letter transmitting this Notice a written statement or 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
Notice of Violation JUN 18 1986 been taken and the results achieved, (4) the corrective step which will be taken to avoid further violations, and (5) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending the response time.
FOR THE NUCLEAR REGULATORY COMMISSION J. Nelson Grace Regional Administrator Dated at Atlanta, Georgia this 1 9 day of June 1986