ML20141J050
| ML20141J050 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 04/11/1986 |
| From: | Wenslawski F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20141J048 | List: |
| References | |
| 50-312-86-05, 50-312-86-5, NUDOCS 8604250278 | |
| Download: ML20141J050 (1) | |
Text
APPENDIX A Sacramento Municipal Utility District Docket No. 50-312 P. O. Box 15830 License No. DPR-54 Sacramento, California 95813 As a result of the inspection conducted during the period of January 16-24, 1986 and telephone calls of February 4, 5, and 19, 1986, and in accordance with NRC Enforcement Policy 10 CFR Part 2, Appendix C, the following violation was identified.
A.
10 CFR Part 50.59(a)(1) states:
"The holder of a license authorizing operation of a production or utilization facility may (i) make changes in the facility as described in the safety analysis report, (ii) make changes in the procedures as described in the safety analysis report, and (iii) conduct tests or experiments not described in the safety analysis report, without prior Commission approval, unless the proposed change, test or experiment involves a change in the technical
~
specifications incorporated in the license or an unreviewed safety question.
Figure 1.1-2 and 1.1-3 of the Final Safety Analysis Report (FSAR) shows an outdoor radwaste storage area. Figures 1.1-2 and 1.1-3 do not show any buildings in the outdoor radwaste storage area.
Section 11.1.5.1.3 of the FSAR describes the area shown on Figure 1.1-2 and 1.1-3 as an area for the storage of solid waste. A building for processing radwaste was erected in the outdoor radwaste storage area in about June of 1985. This building is not shown or described in the FSAR.
Contrary to this requirement, from about June 1985 through January 1986, the building was used to process radwaste and an evaluation was not made of this change to determine that it did not involve an unreviewed safety question or require a change to the Technical Specifications.
This is a Severity Level IV Violation (Supplement I)
Pursuant to the provisions of 10 CFR 2.201, no response is necessary in view of the timely manner in which you corrected this item.
43 11 G36 a1 Dated F. A. Wenslawski, Chief Emergency Preparedness and Radiological Protection Branch 8604P50278 860411 PDR ADOCK 05000312 O
PDR O