ML18005A666
| ML18005A666 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 10/18/1988 |
| From: | Dan Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18005A665 | List: |
| References | |
| 50-400-88-28, NUDOCS 8810280345 | |
| Download: ML18005A666 (3) | |
Text
ENCLOSURE 1
NOTICE OF VIOLATION Carolina Power and Light Company Shearon Harris Docket No. 50-400 License No. NPF-63 During the Nuclear Regulatory Commission (NRC) inspection conducted on August 15-19,
- 1988, and August 30 -
September 2,
1988 violations of NRC requirements were identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions",
(1988), the violations are listed below:
A.
10 CFR 20.201(b) requires each licensee to make or cause to be made such surveys as (1) may be necessary for the licensee to comply with the regulations in this part and (2) are reasonable under the circumstances to evaluate the extent of radiation hazards that may be present.
Health Physics Procedure HPP-030, Control and Release of Equipment/Material from the RCA/Restricted
- Area, Revision 3,
dated August 27, 1987, requires in Section
- 10. 1.1 that material/equipment being transferred within the RCA be surveyed for radiation and contamination per HPP-060, Performance of Radiation and Contamination Surveys.
- Also, Section
- 10. 1.2 states that, if radiation/contamination levels are less than 100 net cpm per probe area as measurable with a thin window pancake-type detector by direct frisk (fixed and removable) and less than MDA (defined as 100 net cpm per 100 cm') for the counting instrument used by smear survey (removable),
the material/equipment can be released for transfer.
Health Physics Procedure HPP-060, Performance of Radiation and Contamination
- Surveys, Revision 2, dated September 29, 1987, requires in Section 7.12 that, when counting smears for beta-gamma contamination using a frisker, a minimum count time of about 20 seconds is recommended to allow for a 90 percent deflection of full scale in the slow response mode.
Also, 10.8.2 requires a frisk of the accessible surfaces of the material being surveyed by moving the probe slowly over the surfaces within one-half inch of the surface.
Contrary to the above, the licensee failed to meet the survey requirements in that, during the week of August 15 - 18,
- 1988, on numerous occasions various items including electrical
- cords, hoses,
- cables, and other pieces of equipment were not adequately surveyed (frisked or smeared) to determine the extent of radiation hazards that may have been present.
This is a Severity Level IV violation (Supplement IV).
881028034 881018 PDR ADOCK 05000400 9
Carolina Power and Light Company Shearon Harris Docket No. 50-400 License No. NPF-63 B.
C.
D.
Technical Specification 6.12 requires that any individual permitted to enter a high radiation area in which the intensity of radiation is equal to or less than 1000 millirem per hour at 18 inches shall be provided with or accompanied by:
1.
a radiation monitoring device that continuously indicates the radiation dose rate in the area; or 2.
a radiation monitoring device that continuously intergrates the radiation dose rate in the area and alarms when a present intergrated dose is received; or 3.
an individual qualified in radiation protection procedures, with a radiation dose rate monitoring device.
Contary to the
- above, the requirements for entry into a high radiation area were not met in that, on August 18,
- 1988, an individiual was observed in a
high radiation area without a radiation monitoring device or accompanied by an individual qualified in radiation protection procedures with a radiation dose rate monitoring device.
This is a Severity Level IV violation (Supplement IV).
Technical Specification 6.8.1 requires that written procedures be established, implemented and maintained covering the Process Control Program implementation.
Technical Specification 6.8.2 requres that each procedure of Technical Specification 6.8.1, and changes
- thereto, be reviewed and approved in accordance with Technical Specification 6.5.1 prior to implementation and reviewed periodically.
Contrary to the above, these requirements were not met in that, procedures covering the Process Control Program were not reviewed and approved prior to implementation and reviewed periodically.
This is a Severity Level IV violation (Supplement IV).
Technical Specification 6.11.1 requires that procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR 20 and shall be
- approved, maintained and adhered to for all operations involving personnel radiation exposure.
Health Physics Procedure HPP-460, Operation of the Dositec
- 502A, Revision 1,
dated June 25,
- 1987, requires in Section
- 6. l.c, that the instrument (Dositec) be response checked prior to issue.
Contrary to the
- above, the licensee failed to adhere to procedures in that, during the period of August 15-17, 1988, Dositecs were not response checked prior to being issued.
Carolina Power and Light Company Shearon Harris Docket No. 50-400 License No.
NPF-63 This is a Severity Level IV violation (Supplement IV).
Pursuant to the provisions of 10 CFR 2.201, Shearon Harris is hereby required to submit a written statement or explanation to the Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555, with a copy to the Regional Administrator, Region II, and a
copy to the NRC Resident Inspector, Shearon
- Harris, within 30 days of the date of the letter transmitting this Notice.
This reply should be clearly marked as a "Reply to a-Notice of Violation" and should include [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, consideration will be given to extending the response time.
If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken.
FOR THE NUCLEAR REGULATORY COMMISSION Dated at Atlanta, Georgia this IB day of ~o4an-1988 m Douglas N. Collins, A ting Director
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Division of Radiation Safety and Safeguards