ML19345E824
| ML19345E824 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/19/1980 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19345E815 | List: |
| References | |
| 50-219-80-28, NUDOCS 8102060212 | |
| Download: ML19345E824 (2) | |
Text
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O APPENDIX A NOTICE OF VIOLATION Jersey Central Power and Light Company Docket No. 50-219 Based on the results of a NRC inspection conducted on August 4-29, 1980, it appears that three of your activities were not conducted in full compliance with the conditions of your NRC Facility License No. DPR-16 as indicated below. These items are infractions.
A.
Technical Specification 6.8.1 states in part, " Written procedures shall be established, implemented, and maintained that meet or exceed the requirements of... Appendix 'A' of the Nuclear Regulatory Comissiun's Regulatory Guide 1.33-1972..."
Regulatory Guide 1.33-1972, Appendix A, Section G.5 lists procedures for protective clothing and for radiation work permits as procedures that should be prepared.
Procedure 915.4, " Contamination Control," Revision 0, states in part, "All personnel entering a contamination controlled area are required to wear protective clothing.
... Required protective clothing will be specified on the Radiation Work Permit..."
Radiation Work Pennit No. 127980 required the user to wear protective clothing consisting of one set of coveralls, surgeon's cap, cotton glove liners, plastic gloves, disposable shoe covers, and rubber shoes while performing activities authorized by the permit.
Contrary to the above, on August 6,1980, four individuals were performing decontamination activities authorized by Radiation Work Permit No. 127980. The decontamination consisted of soap and water washing of equipment and piping in contamination controlled areas of the 51 foot elevation of the reactor building around the core spray booster pumps and the reactor building closed cooling water heat exchangers. The individuals were wearing protective clothing con-sisting only of cotton glove liners, plastic gloves, disposable shoe covers, and surgeon's caps.
None of the individuals were wearing coveralls and one individual was bare chested.
B.
Technical Specification 6.8.1 states in part, " Written procedures shall be established, implemented, and maintained that meet or exceed the requirements of... Appendix 'A' of the Nuclear Regulatory Commission's Regulatory Guide 1.33-1972..."
Regulatory Guide 1.33-1972, Appendix A, Section G.5 lists procedures for protective clothing as procedures that should be prepared.
81 02000 M
Procedure 915.4', " Contamination Control," Revision 0, states in part, "All personnel entering a contamination controlled area are required to wear protective clothing.
... Protective clothing is not to be worn outside the controlled area.
...At exits from contaminated areas, an area is designated as the step off pad. This area...is considered part of the area outside the contaminated area.
Nothing contaminated snould be placed on this area".
Contrary to the above, on August 6,1980, an individual dressed in protective clothing was observed in an area outside a contaminated area.
He had exited a contaminated area, crossed the step off pad and comenced to remove potentially cc taminated protective clothing in a clean area creating the potential for the spread of radicactive contamination.
C.
10 CFR 50 Appendix "B" states in part, "The quality assurance program shall provide control over activities affecting the quality of the identified structures, systems, and components. Activities affecting quality shall be accomplished under suitably controlled conditions.
Controlled conditions include the use of appropriate equipment...
The program shall take into account the need for special controls..."
The Jersey Central Power and Light Company Generation Division Operational Quality Assurance Plan, Revision 3, Appendix A, Quality Assurance Systems List, lists " Liquid, Solid, and Gaseous Radwaste (old plant). Note: The structural elements of the building and those portions of the systems necessary to contain radioactive material and isolate it from the environment are included".
Contrary to the above, a temporary waste water processing demineral-izer was installed in the "old radwaste building" without adequate process controls or monitoring devices to safeguard against the release of radioactive materials to the environment. Subsequently, during system operation, the demineralizer overflowed spilling approximately 20 gallons of radioactively contaminated water, about two gallons of which flowed outside the confines of the building.
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